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JAEA
-DataC
odeJAEA-DataCode
2013-009
日本原子力研究開発機構
Reactor Safety Research UnitNuclear Safety Research Center
October 2013
Japan Atomic Energy Agency 日本原子力研究開発機構
Motoe SUZUKI Hiroaki SAITOU
Yutaka UDAGAWA and Fumihisa NAGASE
InputOutput Manual of Light Water Reactor Fuel
Analysis Code FEMAXI-7 and Its Related Codes
本レポートは独立行政法人日本原子力研究開発機構が不定期に発行する成果報告書です
本レポートの入手並びに著作権利用に関するお問い合わせは下記あてにお問い合わせ下さい
なお本レポートの全文は日本原子力研究開発機構ホームページ(httpwwwjaeagojp)より発信されています
独立行政法人日本原子力研究開発機構 研究技術情報部 研究技術情報課
319-1195 茨城県那珂郡東海村白方白根 2 番地 4電話 029-282-6387 Fax 029-282-5920 E-mailird-supportjaeagojp
This report is issued irregularly by Japan Atomic Energy Agency Inquiries about availability andor copyright of this report should be addressed to Intellectual Resources Section Intellectual Resources Department Japan Atomic Energy Agency 2-4 Shirakata Shirane Tokai-mura Naka-gun Ibaraki-ken 319-1195 Japan Tel +81-29-282-6387 Fax +81-29-282-5920 E-mailird-supportjaeagojp
copy Japan Atomic Energy Agency 2013
i
JAEA-DataCode 2013-009
InputOutput Manual of Light Water Reactor Fuel Analysis Code FEMAXI-7 and Its Related Codes
Motoe SUZUKI Hiroaki SAITOU Yutaka UDAGAWA and Fumihisa NAGASE
Reactor Safety Research Unit Nuclear Safety Research Center Japan Atomic Energy Agency
Tokai-mura Naka-gun Ibaraki-ken
(Received April 18 2013)
A light water reactor fuel analysis code FEMAXI-7 has been developed as an extended
version from the former version FEMAXI-6 for the purpose of analyzing the fuel behavior in
normal conditions and in anticipated transient conditions Numerous functional improvements
and extensions have been incorporated in FEMAXI-7 which are fully disclosed in the code
model description published in the form of another JAEA-DataCode report
The present manual which is the very counterpart of this description document gives
detailed explanations of files and operation method of FEMAXI-7 code and its related codes
methods of inputoutput sample InputOutput methods of source code modification
subroutine structure and internal variables in a specific manner in order to facilitate users to
perform fuel analysis by FEMAXI-7
Keywords LWR Fuel Code Analysis FEM Analysis Numerical Stability Fission Gas Release PCMI Burn-up
ITOCHU Techno-Solutions Corporation (Tokyo)
ii
JAEA-DataCode 2013-009
軽水炉燃料解析コード FEMAXI-7 および関連コードの入出力マニュアル
日本原子力研究開発機構安全研究センター
原子炉安全研究ユニット
鈴木 元衛斎藤 裕明宇田川 豊永瀬 文久
(2013 年 4 月 18 日受理)
FEMAXI-7 は軽水炉燃料の通常運転時及び過渡条件下のふるまい解析を目的と
するコードとして前バージョン FEMAXI-6 に対して多くの機能の追加改良を実施
した高度化バージョンであるこのモデルと内部構造機能の詳細に関する文書は別
の JAEA-DataCode として刊行される本マニュアルはこれと対をなすもので
FEMAXI-7 及び関連コードのファイルの内容入出力の方法サンプル入出力ソー
スの修正方法サブルーチン構造内部変数などについて詳述しFEMAXI-7 による
燃料解析の具体的方法を説明したものである
原子力科学研究所(駐在)319-1195 茨城県那珂郡東海村白方白根 2-4
伊藤忠テクノソリューションズ株式会社
JAEA-DataCode 2013-009
iii
Contents
1Introduction 1
2 Execution file system 1
21 Files of FEMAXI -7 and EXPLOT 1
22 Files of burning analysis code RODBURN-1 2
23 Files of burning analysis code PLUTON 2
24 Compiling source code 3
241 Compiling by Compaq DVF 3
242 Compiling by Intel VF 95 (or upper) 8
243 Compiling by Linux-GNU Fortrang77 13
References 1 and 2 14
3 Execution of program 15
31 On Windows-PC 15
311 Directory structure for Compaq compiler 15
312 Directory structure for Intel compiler 16
313 Basic process of executing the program -1- (Windows) 17
32 Execution in Linux 23
321 Example of Makefile for GNU Fortran 77 (g77) 23
322 Basic process of execution -2- (Linux) 24
33 Performing Re-start function 27
331 Function to bridge full-length rod and short test rod calculations 27
332 Re-start calculation from base-irradiation to test-irradiation 27
333 Name-list parameters related to Re-start calculation 30
334 Variables taken over and those not taken over in Re-start calculation 31
335 Explanations for sample Re-start calculations and method 41
34 Usage of output of burning analysis code RODBURN-1 47
341 Record No and contents 47
342 Usage of records in FEMAXI 48
343 Making input file of RODBURN-1 by using FEMAXI 51
35 Usage of output of burning analysis code PLUTON 51
351 Physical quantities of PLUTON output for FEMAXI 52
352 Structure of inputoutput files of PLUTON 52
353 Contents read by FEMAXI code 63
354 Output file reading function of FEMAXI 65
JAEA-DataCode 2013-009
iv
355 Unit conversion of burnup 68
36 Calculation examples by RODBURN-1 and PLUTON 69
361 PWR fuels 69
362 BWR fuels 75
37 Usage of the Halden data-base TFDB 81
References 3 81
4 FEMAXI-7 Input manual 82
41 Explanation on the relationship of IS and IST 82
411 Function of ISTATE value 82
412 Relationship between IS IST and ISTATE 83
413 Options specified by IS and IST 83
42 Fixed format input 85
43 Name-list Input 88
44 Plot data index IDNO 133
45 Calculated physical quantities in ZERO power state 133
46 Method to input history point data 134
461 Power history data 134
462 Relative power profile 134
463 Input method of power history 135
47 Setting of cladding outer surface temperature 138
5 Models and Input manual of RODBURN-1 141
51 General feature of RODBURN input format 141
52 Some comments on the RODBURN code (Sept1998) 141
53 Explanations of RODBURN-1 models and methods 143 54 Explanation of neutron flux control by ldquoALPH(K) EXTL(K) EXTT(K)
K=1 NDISTrdquo Option for IDIST 149
55 Some important input name-list parameters of FEMAXI-7 for usage
of RODBURN-1 150
56 RODBURN Input data format (1) 151
57 RODBURN Input data format (2) 155
References 5 161
6 Input Manual of Plotting Control Program EXPLOT 163
61 Input parameters for EXPLOT 163
62 Tables of IDNOs classified by variables 166
JAEA-DataCode 2013-009
v
63 Plotting the quantities with common Y-axis 182 64 Explanation on the physical quantities of Y-axis (3) (4)C Group 183
641 Physical quantities of pellet 183
642 Physical quantities of cladding 185
7 Sample InputOutput (numerical and plotted outputs) 187
71 FEMAXI-7 numerical output image of ldquoABC1outrdquo 187 72 Plotting control data file image of ldquoexplotABCrdquo 215
73 Images of plotted output ldquoABC1ABCpdfrdquo 218
74 Example of numerical output of HBS model 224
75 Sample inputoutput of RODBURN-1 226
8 Manual for modification of materials properties models 245
81 Materials properties subroutines 245
82 Method of addition and modification of models 246
821 Density 246
822 Thermal conductivity 246
823 Specific heat 249
824 Thermal expansion 250
825 Youngrsquos modulus 251
826 Poissonrsquos ratio 252
827 Creep 254
828 Fuel pellet swelling 258
829 Densification 260
8210 Plasticity 260
8211 Grain growth 264
8212 Melting point 264
8213 Fission gas release rate and diffusion coefficient 265
8214 Cladding waterside corrosion 265
8215 Cladding irradiation growth 266
8216 Gap thermal conductance 266
8217 He-Xe gas inter-diffusion coefficient 267
83 Method of incorporating a new surface heat transfer model 268
Appendix 273
JAEA-DataCode 2013-009
vi
目 次 1はじめに 1
2 実行ファイルシステム 1
21 FEMAXI -7 および EXPLOT のファイル 1
22 燃焼計算コード RODBURN-1 のファイル 2
23 燃焼計算コード PLUTON のファイル 2
24 ソースコードのコンパイル 3
241 Compaq DVF によるコンパイル 3
242 Intel VF 95 (or upper)によるコンパイル 8
243 Linux-GNU Fortrang77 でのコンパイル 13
参考文献 1 2 14
3 プログラムの実行 15
31 Windows-PC の場合 15
311 Compaq compiler の場合のディレクトリ構造 15
312 Intel compiler の場合のディレクトリ構造 16
313 基本的な実行の順序 -1-(Windows) 17
32 Linux での実行 23
321 GNU Fortran 77 (g77) の場合の Makefile 例 23
322 基本的な実行の順序 -2-(Linux) 24
33 Re-start 機能の実行 27
331 長尺燃料棒と短尺試験燃料棒の計算をつなぐ計算 27
332 ベース照射から試験照射への Re-start 計算 27
333 Re-start 計算に関係する Name-list パラメータ 30
334 Re-start 計算に引き継がれる変数と引き継がれない変数 31
335 サンプル Re-start 計算と方法の説明 41
34 燃焼計算コード RODBURN-1 の出力の利用 47
341 レコード Noと内容 47
342 FEMAXI でのレコード利用法 48
343 FEMAXI を用いて RODBURN-1 の入力ファイルを作る方法 51
35 燃焼計算コード PLUTON の出力の利用 51
JAEA-DataCode 2013-009
vii
351 PLUTON と FEMAXI の物理量の関係 52
352 PLUTON の入出力ファイルの構造 52
353 FEMAXI コードに読み込まれる内容 63
354 FEMAXI による出力ファイル読み込み機能 65
355 燃焼度の単位変換 68
36 RODBURN-1 と PLUTON の計算例 69
361 PWR 燃料 69
362 BWR 燃料 75
37 Halden データベース TFDB の利用 81
参考文献 3 81
4 FEMAXI-7 入力マニュアル 82
41 IS と IST の関係に関する説明 82
411 ISTATE 値の機能 82
412 IS IST および ISTATE の間の関係 83
413 IS と IST によって指定されるオプション 83
42 固定フォーマット入力 85
43 Name-list 入力 88
44 プロットデータインデックス IDNO 133
45 ZERO パワー状態の計算データ 133
46 履歴データの入力方法 134
461 出力の履歴点データ 134
462 発熱密度プロファイル 134
463 出力履歴の入力方式 135
47 被覆管外表面温度の入力設定モード 138
5 RODBURN-1 のモデルと入力 141
51 RODBURN 入力フォーマットの一般的特徴 141
52 RODBURN コードに関するコメント 141
53 RODBURN-1 のモデルと方法の説明 143
JAEA-DataCode 2013-009
viii
54 ldquoALPH(K) EXTL(K) EXTT(K) K=1 NDISTrdquo IDIST オプションによる
中性子束制御の説明 149
55 RODBURN-1 を使う際の FEMAXI-7 のいくつかの重要な
name-list パラメータ 150
56 RODBURN 入力データフォーマット(1) 151
57 RODBURN 入力データフォーマット(2) 155
参考文献 5 161
6 プロット制御プログラム EXPLOT 入力マニュアル 163
61 EXPLOT の入力パラメータ 163
62 変数によって分類された IDNO のテーブル 166
63 Y 軸共通物理量プロットの使用法 182
64 プロットデータの Y 軸物理量(3)(4)C グループに関する説明 183
641 ペレット物理量 183
642 被覆管物理量 185
7 サンプル入出力(数値出力+プロット図) 187
71 FEMAXI-7 数値出力 ABC1out イメージ 187
72 プロット出力制御データ explotABC イメージ 215
73 プロット出力 ABC1ABCpdf イメージ 218
74 HBS モデルの出力数値ファイル例 224
75 RODBURN-1 入出力サンプルケース 226
8 物性値モデルの修正マニュアル 245
81 物性値ルーチン 245
82 物性値の追加修正方法 246
821 密度 246
822 熱伝導率 246
823 比熱 249
824 熱膨張 250
825 ヤング率 251
JAEA-DataCode 2013-009
ix
826 ポアソン比 252
827 クリープ 254
828 スエリング 258
829 焼きしまり 260
8210 塑性 260
8211 結晶粒成長 264
8212 融点 264
8213 FP ガス放出率と拡散係数 265
8214 被覆管腐食 265
8215 被覆管照射成長 266
8216 ギャプコンダクタンス 266
8217 He-Xe ガス相互拡散係数 267
83 新しい表面熱伝達モデルの組み込み法 268
付録 273
This is a blank page
JAEA-DataCode 2013-009
- 1 -
1 Introduction Fuel analysis code FEMAXI-7 is the latest version which has been extended to cope with a wide variety of LWR fuel behavior analyses by using related auxiliary codes system and compilers The present manual makes a pair with another JAEA-DataCode 2013-005(11) a model description of FEMAXI-7
The authors hope that this manual will serve for a wide circle of users in understanding and operating FEMAXI-7 with proficiency Users are recommended to ask JAEA freely concerning the contents when they come across any problem
2 Execution file system The method of installing FEMAXI(21) system into Windows PC and Linux systems and
execution of the program are explained
21 Files of FEMAXI-7 and EXPLOT The source files of FEMAXI-7 and plotting program EXPLOT consist of the files listed in
Table 211 and Table 212 The source file group of FEMAXI-7 is represented by
Femaxi7FOR in Table 211 and the group of EXPLOT is listed in Table212 A sample
calculation case ID is named ldquoABCrdquo corresponding to the sample case presented later in
chapter 7 FEMAXI-7 reads the input file name from a file-name-description file fnamed
and opens the required files The file names are specified including the path and designated in
the order of the unit No listed in Table 211 (Refer to section 311 )
Table 211 FEMAXI-7 files Unit No File (default name) Contents
Femaxi7FOR Source code including all the modules
- fem2exe Executable program
5 ABCd05 (ft05d) Sample input file
6 ABCout (ft06d) Sample numerical output file
7 ABCplt (expldat) Sample plotting data file
9 fnamed File-name-description file
55 formdata Name-list input format file
89 ft89d Steam table library file
Since EXPLOT uses calcomp-compatible instructions it is necessary to link the program
with a calcomp compatible library pltcmplib (in Linux calcmpa) in compiling
explotfor
JAEA-DataCode 2013-009
- 2 -
Table 212 EXPLOT files Unit No File (default name) Contents
- explotfor explot2exe Source executable program
5 pltcal8lib (or calcmpa) Calcomp-compatible library
6 explotd Plotting control file
7 ABCplot ABCps ABCpdf Sample output Explained in Chap7
22 Files of burning analysis code RODBURN-1 RODBURN-1 is a simplified and convenient burning analysis code for LWR fuel rods(21)
The source files of RODBURN-1 are listed in Table 221 This code calculates the power
density profile in the radial direction of pellet as a function of average burnup and concurrently
calculates the generated amounts of fission products and He RODBURN-1 uses a
file-name-description file rfnamed similarly to FEMAXI
FEMAXI and RODBURN open the files collectively at the head of main program
Accordingly it is easy for users to change the default file names and path to adjust them to their
own system circumstances
Table 221 RODBURN-1 files Unit No File name (default name) Contents
- rodburnfor
rodburnexe
RODBURN source executable program
5 ABCrddat Input data file (sample) (renamed from rodin) 6 ABCrdout Numerical output file (sample) 7 ABCrodex Result data file to be read by FEMAXI 9 rfnamed File-name-description file 1 ft01d RABBLE(23) original library 1 2 ft02d RABBLE original library 2
60 EJU268 Resonance parameters for U-268 and group cross section of WIMS69(24)
61 EJPU240 Resonance parameters for Pu-240 and group cross section of WIMS69
66 origend ORIGEN(25) code library
23 Files of burning analysis code PLUTON PLUTON (=PLUTON-PC) is a burning analysis code for LWR fuels(22) This code has a
variety of calculation contents and output formats by using more precise models and methods
than those of RODBURN When a result file generated by PLUTON is used by FEMAXI-7
JAEA-DataCode 2013-009
- 3 -
either one of two methods should be selected to write the numerical figures of the result file at
the end of input file of FEMAXI or to read the result file into FEMAXI To read the result file
file fmdt is read which is given from PLUTON In an example shown later it has a unit No
of 51 to be read as ABCfmdt
24 Compiling source code 241 Compiling by Compaq DVF
It was a standard compiling method for FEMAXI-V and -6 EXPLOT RODBURN and
PLUTON to be compiled with Compaq Digital Visual Fortran 61 or Upper-version (CDVF)
However CDVF has been discontinued Accordingly hereafter Intelreg Visual Fortran
(IVF)(27) is used as a standard compiler for FEMAXI-7 EXPLOT RODBURN and PLUTON
Nevertheless compiling method with CDVF is explained first as there may be still not so
small a number of users of CDVF The compiling options of CDVF are shown below for
Windows PC (2000 XP Vista and Windows 7) Here the optimization parameter for CDVF
compiling is ldquoFull optimizationrdquo
(1) Basic method on the basis of Developer Studio In the following example Compaq Visual Fortran Standard Edition 660 (English
version) is used The example is also applicable to Compaq Visual Fortran Ver 61 or Upper
1) Making a new project To form a new project open a new project making pane by selecting the menu
[File][New] Select [Fortran Console Application] by [Projects] tab and input [Project
name] eg if the source is FEMAXI ldquoFEMrdquo
Input the directory name in [Location] where project is generated or select a parent
directory name under which the project directory name is input then click [OK] In the
example below ldquoCFEM7rdquo is selected and the project directory is named ldquoCFEM7FEMrdquo
then [OK] is clicked In the next selection pane select [An empty project] click [Finish] and
click [OK] in the pane [New Project Information]
JAEA-DataCode 2013-009
- 4 -
2) Designation of source code Designate the source code in ldquoFile Viewrdquo pane If no ldquoFile Viewrdquo pane is shown show the
pane by selecting [View][Workspace] In the pane extend the workspace files selected in
the previous process 1) Right click on [Source Files] and select [Add Files to Folder] and
then select the source files by [Insert Files into Project] In the example below the compile
target code is FEMAXI-7 and ldquoFEMAXI7FORrdquo is selected
3) Change into Release mode Change the build configuration into ldquoReleaserdquo mode Select the menu [Build][Set
Active Configuration] open [Set Active Project Configuration] pane and change the mode into [FEM - Win32 Release]
JAEA-DataCode 2013-009
- 5 -
4) Designation of other INCLUDE directories If there are some INCLUDE files in a directory except the directory directly under the
project directory it is necessary to designate the INCLUDE directory one more time
This process is as follows select [Project][Settings] to open the pane [Project
Settings] Set [Settings For] into [Win32 Release] (or to [All Configurations] ) and select
the uppermost ranked project name in the file structure viewing pane below Change the
pane into [Fortran] tab and change [Category] into [Preprocessor] Input the directory name
which has the INCLUDE files into [INCLUDE and USE Paths] In this example ldquoINCrdquo is
designated
JAEA-DataCode 2013-009
- 6 -
5) Libraries
For EXPLOT it is necessary to designate a calcomp library for compiling before building Detailed procedure is explained in the next sections (3) and (4)
6) Building the executable files
Perform building to make an executable program by selecting [Build][Build FEMexe (=executable program name)]
7) Confirmation of executable program generation Confirm that the executable program has been generated under ldquoReleaserdquo directory in the
project directory (2) Designation method of linking Calcomp library in Developer Studio
In EXPLOT either one of the two following methods is used in designating the calcomp
JAEA-DataCode 2013-009
- 7 -
library It is not necessary to use both the methods at the same time
1) Addition of library file by changing link setting Link pltcal by adding library file in setting the link of project By selecting
[Project][Settings] open the pane [Project Settings] Select [Win32 Release] (or [All
Configurations]) and select the uppermost project name (ldquoexplot2rdquo) in the directory
structure table pane shown below Shift to the tab [Link] put a half space after the already
registered library in [Objectlibrary modules] and input the library path ie in this example
ldquopltcal8librdquo for this file is stored just under the project directory
2) Addition of library file by adding resource file
Addition of library file to Resource File allows the link Right-click [Resource Files] in
View Files pane select [Add Files to Folder] and open [Insert Files into Project] pane
Change the [File type] into [Library Files(lib)] and select ldquopltcal8librdquo
JAEA-DataCode 2013-009
- 8 -
242 Compiling by Intel VF 95 (or upper)
Method to compile the source by Intel Visual Fortran(27) is described below It is necessary
to change the settings of retention of error check variables and local variables from the initial
settings which is different from the situation in Compaq Visual Fortran
(1) Basic method of compiling FEMAXI-7 on Visual Studio In the following example Intel Visual Fortran Compose XE 2011 on Microsoft Visual
Studio 2010 is used This example is also applicable to Intel Visual Fortran 95 without
significant changes
1) Making project Select [File][New Project] extend [Intel(R) Visual Fortran] and select [Console
Application] and select [Empty Project] Put a project name eg [FEM] and location of the
project and click [OK]
JAEA-DataCode 2013-009
- 9 -
2) Addition of source files Right-click the [source files] of the project in [Solution Explorer] select
[Addition][Existing files] A file pane opens Select source files and click [Addition]
3) Change into Release mode Change the build-configuration into Release mode by opening [Build] pane
[Configuration Manager]
JAEA-DataCode 2013-009
- 10 -
4) Addition of include file Method A Select [Project][Properties] Spread [Fortran] of configuration properties and
designate the include file names or their directory name by clicking [General][Additional Include Directories]
Method B Add the include files to the [Header Files] in Solution Explorer pane
5) Change of settings to cover fortran 77
When compiling FEMAXI-7 EXPLOT and RODBURN by Intel Fortran the following
changes are needed because the source files are partly written in Fortan77 Since PLUTON is
written in Fortran 90 these changes are not necessary
Select [Project][Properties] and spread [Fortran]
i) Spread [Diagnostics][Language Usage Warnings] input [No] in [Check Routine Interfaces]
JAEA-DataCode 2013-009
- 11 -
ii) [Data][Local Variable Storage] change to [All Variables SAVE (Qsave)]
iii ) Open [External Procedure] confirm that [Calling Convention] is [Default]
JAEA-DataCode 2013-009
- 12 -
iv) [Run-time]input [No] in [Check Array and String Bounds]
v) Spread [Diagnostic][General] input [No] in [Interface Block Generation]
This option is not present in Intel Visual Fortran Composer XE 2011
When all the changes are done click [Apply]
6) Making an executable file Make an executable program by [Build][Build Project name]
(2) Method of compiling EXPLOT on Visual Studio 1) Addition of source file and library file Similarly to the case of FEMAXI-7 above add the source code and library by using [Solution Explorer] pane
JAEA-DataCode 2013-009
- 13 -
2) Change of settings to cover fortran 77 All the changes described above in 5) for FEMAXI-7 should be also applied to EXPLOT 3) Making an executable file
Make an executable program by [Build][Build Project name] 243 Compiling by Linux-GNU Fortran g77
To execute FEMAXI-7 on Linux compiling procedure by g77 which can be obtained for
free is explained Only FEMAXI and EXPLOT are assured to be successfully built by g77
(1) FEMAXI compiling
In an usual setting of g77 initialization and retention of local variables is not conducted so that it is necessary to add retention of local variables as optional arguments(-fno-automatic)
and initialization (-finit-local-zero) when compiling Accordingly femaxi7FOR is compiled
by the commands below to make an executable program FEMAXI-7
g77 -o FEMAXI-7 -fno-automatic -finit-local-zero femaxi7FOR (2) Building the executable file of EXPLOT
CALCOMP-compatible library calcmpa is generated from source file calcmpfor
g77 -fno-automatic -finit-local-zero -o calcompfor -c calcmpo ar cr calcmpo calcmpa
By linking CALCOMP-compatible library link is carried out
g77-o EXPLOT -fno-automatic -finit-local-zero explot2for calcmpa
JAEA-DataCode 2013-009
- 14 -
References 1 and 2 (11) M Suzuki H Saitou Y Udagawa and F Nagase Light Water Reactor Fuel Analysis
Code FEMAXI-7 Model and Structure JAEA-DataCode 2013 ndash 005(2013) (21) MSuzuki HSaitou YUdagawa ldquoLight Water Reactor Fuel Analysis Code
FEMAXI-7Model and Structurerdquo JAEA-DataCode 2010-035 (2011) [in Japanese] (22) MUchida HSaitou ldquoRODBURN A Code for Calculating Power Distribution in Fuel
Rodsrdquo JAERI-M 93-108 (1993) [in Japanese] (23) PHKier and AARobba ldquoRABBLE A Program for Computation of Resonance
Absorption in Multi-region Reactor Cellsrdquo ANL-7326 (1967) (24) WIMS-D IAEA Nuclear Data services httpwww-ndsiaeaorg (25) MJBell ldquoORIGEN-The ORNL ISOTOPE GENERATION AND DEPLETION CODErdquo
ORNL-4628 (1973) (26) SLemehov and MSuzuki ldquoPLUTON ndash Three-Group Neutronic Code for Burnup
Analysis of Isotope Generation and Depletion in Highly Irradiated LWR Fuel Rods JAERI-DataCode 2001-025 (2001)
(27) Intel reg Visual Fortran Composer XE 2011 Windows httpwwwxlsoftcomjpproductsintelcompilersfcwindexhtmltab=0
JAEA-DataCode 2013-009
- 15 -
FemReleasefem2exe FEMdsp FEMdsw FEMopt FEMplg of Compaq DVF
formdata (description of output variables) ft89d Fem srcf INC (source and include files)
3 Execution of program
31 On Windows-PC 311 Directory structure for Compaq compiler
An example of directory structure and file configuration is shown for Windows system assuming that the parent directory CFem7 is located on C-drive
CFem7
Plot2 explot2Releaseexplot2exe Pltcal8lib (Calcomp library) explot2dsp explot2dsw explot2plg explot2opt
RODReleaserodburn2exe rodburn2for (RODBURN-1 source) Ejpu240 Eju238 ft01d ft02d origend (library)
rodburn2dsp rodburn2dsw rodburn2plg rodburn2opt of Compaq DVF
rbout rodex (ORDBURN result file to be fed to FEMAXI)
outp out (FEMAXI numerical output) plt (plotting data file generated by FEMAXI) ps (postscript file of plotted figures) pdf (plotted figures in pdf file converted from ps file) plot (text file of numerical data of plotted figures) csv (CSV file of plotted numerical data) rdout (numerical output of RODBURN-1)
Wrk rodbat fembat plotbat (batch programs) d05 (FEMAXI input file) rddat (RODBURN input file) explot (plotting control file) mytitltxt (plotting caption file)
JAEA-DataCode 2013-009
- 16 -
FemReleaseFEMexe FEMsln FEMvfproj of Intel compiler formdata (description of output variables) ft89d (library)
Fem srcf INC (source and include files)
312 Directory structure for Intel compiler
An example of directory structure and file configuration is shown for Windows system assuming that the parent directory Fem7 is located on C-drive
CFem7
Plot2 explot2Releaseexplot2exe explot2 Pltcal8lib (Calcomp library)
explot2sln explot2ncb explot2opt explot2vfproj of Intel compiler
RODRelease RODexe rodburn2for (RODBURN-1 sources) Ejpu240 Eju238 ft01d ft02d origend (libraries) RODsln RODvfproj of Intel compiler
rbout rodex
outp out (FEMAXI numerical output file) plt (plotting data file generated by FEMAXI) ps (postscript file of plotted figures) pdf (plotted figures in pdf file converted from ps file) plot (text file of numerical data of plotted figures) csv (CSV file of plotted numerical data) rdout (numerical output of RODBURN-1)
Wrk rodbat fembat plotbat d05 (FEMAXI input file) rddat (RODBURN-1 input file) explot (plotting control file) mytitltxt (plotting caption file)
JAEA-DataCode 2013-009
- 17 -
313 Basic process of executing the program -1- (Windows)
An important process to execute the FEMAXI-7 system is briefly explained below
(1) Activation of command prompt FEMAXI-7 RODBURN and EXPLOT are executed by entering a batch command
following the MS-DOS prompt For this purpose MS-DOS Windows for the FEMAXI
system has to be prepared
A) Look for the MS-DOS prompt icon in the Windows system create a shortcut to the
program to be executed and place it on Desktop
B) Open ldquoPropertiesrdquo of this shortcut press the program tab select eg CFem7Wrk from
the Work Directory
C) Change the icon to enable easy recognition of this shortcut and simultaneously change
the name of the shortcut to ldquoFem7rdquo Hereafter this shortcut is called ldquoFEM7rdquo
(2) Test run of RODBURN-1
A) Input ldquorod ABCrdquo following the prompt (Fem7Wrk) which causes RODBURN to be
executed By entering ldquorod ABCrdquo the system searches for the file ldquoABCrddatrdquo and
reads it If ldquorod ABCrddatrdquo is entered the system searches for ldquoABCrddatrddatrdquo
and ldquoError stoprdquo occurs because such a file does not exist
B) After the completion of execution start Explorer and confirm if the time stamp of the
file ABCrodex in Wrk RBOUT is renewed
(3) Test run of FEMAXI-7
A) Enter ldquofem ABC 1rdquo following the prompt which causes FEMAXI-7 to be executed
By entering ldquofem ABC 1rdquo the system searches for the file ldquoABCd05rdquo reads it and
outputs the files named ABC1out and ABC1plt When ldquofem ABC 2rdquo is entered first
ABC2out and ABC2plt are created
If ldquofem ABCd05rdquo is entered the system searches for the file ldquoABCd05d05rdquo and
ldquoError stoprdquo occurs because such a file does not exist
B) After the completion of execution start Explorer and confirm if files ABC1out and
ABC1plt are created in Wrk Outp
JAEA-DataCode 2013-009
- 18 -
(4) Test run of EXPLOT
A) Enter ldquoplot ABC1 drdquo following the prompt which causes EXPLOT to be executed By
entering ldquoplot ABC1 drdquo the system searches for and reads files ldquoexplotdrdquo and
ldquoABC1pltrdquo By entering ldquoplot ABC1pltrdquo the system searches for a file ldquoABC1pltpltrdquo
and ldquoError stoprdquo occurs because such a file does not exist When ldquoplot ABC2 frdquo is
entered the files ldquoexplotfrdquo and ldquoABC2pltrdquo are read and the files ABC2plot ABC2ps
and ABC2csv are produced
B) After the completion of execution start Explorer and confirm if files ABC1plot
ABC1ps and ABCcsv are created in Wrk OUTP
C) After this confirmation double click ABC1ps which activates Adobe Acrobat Distiller
and the system converts the ps file into a pdf file After conversion has been completed
the file ABC1pdf is created To enable this conversion it is necessary to install either
the complete set of Adobe Acrobat 40 (or a higher version) or ps2pdf ps2pdf can be
used by downloading from internet without charge installing and setting GhostScrpipt
After setting GhostScrpipt move to Fem7WrkOUTP and input the ps2pdf command
ldquops2pdf ABC1ps ABC1pdfrdquo Then ABC1pdf can be generated from ABC1ps
The above-mentioned conversion cannot be carried out using Acrobat Reader which
can be downloaded without charge
D) Double click ABC1pdf and open the file to confirm the creation of output plots
(5) Main analysis -1- (case1 making input file for RODBURN by using FEMAXI)
A) Initially FEMAXI calculation is carried out without RODBURN Namely calculation
is carried out with the name-list parameter IROD=1 or =2 or =3 in input data file (eg
EFGd05) For the value of IROD see the input manual of FEMAXI-7 Then FEMAXI
does not perform normal calculation but generates a file ldquorodinrdquo in Wrk
B) Open the file ldquorodinrdquo and confirm the content Rename ldquorodinrdquo into eg ldquoABCrddatrdquo
and execute RODBURN with this input file ABCrddat
C) Next to perform calculations using the results of RODBURN execute FEMAXI again
by setting the name-list parameters IROD=0 and IFLX= -2 in EFGd05
D) Edit the plot control information file explotd
JAEA-DataCode 2013-009
- 19 -
E) Execute EXPLOT and produce EFGps and EFplot Obtain plotted figures by
converting EFGps into EFGpdf
F) Note Since the output files EFGout EFGplt EFGplot EFGps and EFGpdf are
overwritten each time E) through F) are executed if users wish to retain previous results
they should be assigned a convenient name such as EFG1out
(6) Main analysis -2- (case2 making input file for RODBURN)
A) When the output history in the input data file (eg EFGd05) is time vs linear power
FEMAXI calculation is initially carried out without RODBURN Namely calculation
is carried out with the name-list parameter IFLX=0
B) Open the output file EFGout using an editor read the cumulative burnup and produce
the RODBURN input data file EFGrddat After this follow the identical processes to
those shown in the case1above
(7) Main analysis -3- (case3 using PLUTON) By designating the name-list parameter IFLX=-1 FEMAXI calculation is performed with
the burning analysis result file obtained by PLUTON-PC execution
JAEA-DataCode 2013-009
- 20 -
(8) List of batch files A) Execution of FEMAXI fembat
In a case where different parent directory from FEM7 is used change the 3rd line ldquoset
MYPATH=CFEM7rdquo
rem FEMAXI Execution Started
setlocal
set MYPATH=CFEM7
IF 2 == GOTO NOX1
echo D05 MYPATHWrk1d gt fnamed
echo OUT MYPATHWrkoutp12out gtgt fnamed
GOTO NOX2
NOX1
rem ERROR
rem 2 argments are required
rem ( ex if input file name is arg1rns )
rem ( ranbat arg1 arg2 )
exit
NOX2
del MYPATHWrkoutp12plt
del MYPATHWrkoutp12plt2
echo PLT MYPATHWrkoutp12plt gtgt fnamed
echo FT11 MYPATHWrkoutp12ft11 gtgt fnamed
echo FT18 MYPATHWrkoutp12ft18 gtgt fnamed
echo FT20 MYPATHWrkoutp12max gtgt fnamed
echo PLUTN MYPATHWrkrbout1FMdt gtgt fnamed
echo RODEX MYPATHWrkrbout1rodex gtgt fnamed
echo FORM MYPATHFemformdata gtgt fnamed
echo FT89 MYPATHFemft89d gtgt fnamed
copy MYPATHWrk1d05 1d
copy MYPATHWrkoutp1ft11 ft15d
MYPATHFemReleaseFem
del fnamed
del 1d
del FT90d
del ft10d
del ft16d
del ft17d
endlocal
rem FEMAXI Calc completed
JAEA-DataCode 2013-009
- 21 -
B) Execution of RODBURN rodbat
echo RODBURN Execution Started
setlocal
set MYPATH=CFEM7
echo MYPATHwrk1d gt rfnamed
echo MYPATHwrkoutp1rdout gtgt rfnamed
echo MYPATHwrkrbout1rodex gtgt rfnamed
echo MYPATHRODft01d gtgt rfnamed
echo MYPATHRODft02d gtgt rfnamed
echo MYPATHRODeju238 gtgt rfnamed
echo MYPATHRODejpu240 gtgt rfnamed
echo MYPATHRODorigend gtgt rfnamed
copy MYPATHwrk1rddat 1d
cMYPATHRODReleaserodburnexe
del rfnamed
del 1d
del wk
del rbpldat
endlocal
echo RODBURN Calc completed
JAEA-DataCode 2013-009
- 22 -
C) Execution of EXPLOT plotbat
rem PLOT6 Execution Started
setlocal
set MYPATH=CFEM8
move MYPATHWrkoutp1plt 1plt
move MYPATHWrkoutp1plt2 1plt2
echo 1plt gtgt expd
IF 2 == GOTO NOX
copy MYPATHWrkexplot2 explotd
echo 12ps gt exp2d
NOX
MYPATHexplot2Releaseexplot2exe
copy plotps MYPATHWrkoutp12ps
copy plotout MYPATHWrkoutp12plot
copy plotd MYPATHWrkoutp12csv
copy ft22d MYPATHWrkoutp12last
move 1plt MYPATHWrkoutp1plt
move 1plt2 MYPATHWrkoutp1plt2
del plotps
del plotd
del plotout
del expldat
del expd
del exp2d
del ft05d
del explotd
endlocal
rem PLOT6 Calc completed
JAEA-DataCode 2013-009
- 23 -
32 Execution in Linux
321 Example of Makefile for GNU Fortran 77 (g77) An example of Makefile of Gnu-make is shown which assumes the directory structure
shown in section 321 The makefile having the following contents is put just under the
directory $HOME$FEM7 and by executing ldquomake FEMAXI7rdquo or ldquomake EXPLOTrdquo
compilation can be performed with g77 In the case below compilation is performed with O2
optimization and static
FEMAXI-7 Makefile(GNU-make)
fortran compiler
FC = g77 -static
include directory
INC = INC
INCP = PLOT2inc
LIBP = PLOT2calcompa
fortran compile flag
OFLAG = -o
FFLAGS = -O2 -I$(INC) -w -fno-automatic -finit-local-zero
FFLAGSP = -O2 -I$(INCP) -w -fno-automatic -finit-local-zero
FFLAGL = -w -fno-automatic -finit-local-zero
FEM = FEM
PLOT2 = PLOT2
SRC = srcf
SRCFEM = $(SRC)femaxi7for
SRCPLOT= $(PLOT2)explot2for
CALCOMP= $(PLOT2)calcmpfor
OBJFEM = $(SRC)femaxi7o
OBJPLOT = $(PLOT2)explot2o
OBJCALCOMP = $(PLOT2)calcmpo
$(OBJFEM) $(SRCFEM)
$(FC) $(FFLAGS) $(OFLAG) $ -c $lt
$(OBJPLOT) $(SRCPLOT)
$(FC) $(FFLAGSP) $(OFLAG) $ -c $lt
$(OBJCALCOMP) $(CALCOMP)
$(FC) $(FFLAGL) $(OFLAG) $ -c $lt
$(LIBP) $(OBJCALCOMP)
ar cr $ $lt
FEMAXI7 $(OBJFEM)
$(FC) $(OBJFEM) $(FFLAGS) $(OFLAG) $(FEM)$
EXPLOT $(OBJPLOT) $(LIBP)
$(FC) $(OBJPLOT) $(OFLAG) $(PLOT2)$ $(LIBP)
JAEA-DataCode 2013-009
- 24 -
322 Basic process of execution -2- (Linux)
By executing a script file in a terminal emulator FEMAXI-7 and EXPLOT can be run In
the following explanation executing method is described on the assumption that the related
files FEM7 are present in the directory which is just below the home directory $HOMES$
The directory structure of Linux system for FEMAXI is similar to those of the Windows
system
[Attention] execution is capable of failure except the case where line feed encode is LF
(1) Process of FEMAXI-7 execution A) Activate the terminal emulator and move the current directory into $HOME$FEM7Wrk
by the command ldquocd FEM7Wrkrdquo
B) Activate FEMAXI by the script file femsh Put an input file eg ABCd05 under $HOME$FEM7Wrk and input ldquofemsh ABC 1rdquo in the terminal emulator The shell script is run ABCd05 is read and files ABC1 are output Here it is noted that by entering ldquofemsh ABCf05 1rdquo the system searches for ABCd05d05 and ldquoError stoprdquo occurs because such a file does not exist
C) After the completion of execution confirm if files ABC1out and ABC1plt are created in
$HOME$FEM7Wrkoutp
(2) Process of EXPLOT execution A) Activate the terminal emulator and move the current directory into $HOME$FEM7Wrk
by the command ldquocd FEM7Wrkrdquo
B) Activate EXPLOT by the script file explotsh If plt file of FEMAXI eg ABC1plt exists under the directory $HOME$FEM7Wrkoutp and EXPLOT input file explotd exists under the directory $HOME$FEM7Wrk input ldquoplotsh ABC1 drdquo in the terminal emulator Then shell-script is executed reads ldquoABC1pltrdquo and ldquoexplotdrdquo and creates a file ABC1 under the directory $HOME$FEM7Wrkoutp Here it is noted that by entering ldquoplotsh ABC1pltrdquo the system searches for ABC1pltplt and ldquoError stoprdquo occurs because such a file does not exist
C) After the completion of execution confirm if files ABC1plot ABC1ps and ABC1csv are
created in $HOME$FEM7Wrkoutp If ps2pdf has been installed in the system
ABC1pdf is also created
JAEA-DataCode 2013-009
- 25 -
(3) Contents of shell-script A) Execution of FEMAXI femsh
binsh
echo FEMAXI Execution Started
echo D05 $1d gtgt fnamed
echo OUT outp$1$2out gtgt fnamed
rm outp$1$2plt
rm outp$1$2plt2
echo PLT outp$1$2plt gtgt fnamed
echo FT11 outp$1$2ft11 gtgt fnamed
echo FT18 outp$1$2ft18 gtgt fnamed
echo FT20 outp$1$2max gtgt fnamed
echo PLUTN rbout$1FMdt gtgt fnamed
echo RODEX rbout$1rodex gtgt fnamed
echo FORM FEMformdata gtgt fnamed
echo FT89 FEMft89d gtgt fnamed
cp $1d05 $1d
FEMFEMAXI-7
rm fnamed
rm $1d
rm FT90d
rm ft10d
rm ft16d
rm ft17d
echo FEMAXI Calc completed
JAEA-DataCode 2013-009
- 26 -
B) Execution of EXPLOT plotsh
plotsh
echo PLOT Execution Started
mv outp$1plt $1plt
mv outp$1plt2 $1plt2
echo $1plt gtgt expd
cp explot$2 explotd
echo $1$2ps gt exp2d
PLOT2EXPLOT
cp plotps outp$1$2ps
cp plotout outp$1$2plot
cp plotd outp$1$2csv
cp ft22d outp$1$2last
mv $1plt outp$1plt
mv $1plt2 outp$1plt2
rm plotps
rm plotd
rm plotout
rm expldat
rm expd
rm exp2d
rm ft05d
rm explotd
echo PLOT6 Calc completed
ps2pdf outp$1$2ps outp$1$2pdf
JAEA-DataCode 2013-009
- 27 -
33 Performing Re-start function A new Re-start function has been implemented in FEMAXI-7 This function generates a result file ie Re-start file which stores the EOL conditions of fuel rod after calculation along base-irradiation history and can be read by FEMAXI-7 to perform re-start calculation Hereafter the first calculation to generate the Re-start file is referred to as ldquoBase calculationrdquo and the calculation following the re-start is referred to as ldquoRe-start calculationrdquo 331 Function to bridge full-length rod and short test rod calculations
In the analysis of a full length fuel rod which was base-irradiated in a commercial reactor and refabricated into a short instrumented rod to be test-irradiated in a test reactor a short rod geometry was obliged to be adopted from the beginning of base-irradiation by the analyses of previous versions of FEMAXI up to FEMAXI-6 This analytical restraint has been removed
(1) In base-irradiation calculation is performed with a full length rod geometry including
pellet stack length and plenum length etc(IFEMRD=1 or 0) In this case users have to
set a plural of segments in the axial direction of rod and this axial segmentation should be
conducted so that length and location of a short test rod portion are included in the axial
segments of base-irradiation analysis
(2) In the input file of FEMAXI where a full length rod is divided into 6 segments (more than 2 segments) by designating IREST=4 for example the rod conditions at the end of base-irradiation in all the segments are stored in Re-start file ft11 This file is usually generated in the directory WrkOUTP
332 Re-start calculation from base-irradiation to test-irradiation
(1) Renaming Re-start file Implication of the file name of ft11 is explained below Suppose a file Base1ft11 is generated after Base calculation(BC) This requires the input file name of Restart calculation (RC) to be Base1d05 However it often happens that RC is applied to test irradiation calculation and its input file is named Testd05 or something similar Consequently it is necessary to rename Base1ft11 into Testft11 If this Restart calculation uses a RODBURN result file the result file named baserodex exists in RBOUT Then it is necessary to make a duplicate of baserodex in another directory rename it into Testrodex or something similar and return it back to RBOUT Otherwise Re-start calculation will not run with input file Testd05
JAEA-DataCode 2013-009
- 28 -
It is often possible to use the same rodex file in both base calculation and Re-start calculation RODBURN performs calculation until the burnup which is to some extent higher than the burnup at EOL which is specified by input file On the other hand the additional burnup during the test irradiation (Re-start calculation) is not very large Accordingly in many cases the burnup extension in the Re-start irradiation falls within the range of burnup of rodex file calculated by RODBURN
Even if the burnup of test irradiation exceeds the maximum burnup of rodex the calculation will not be significantly affected for the following reason
If the burnup of FEMAXI calculation exceeds the upper bound recorded in rodex file FEMAXI continues calculation assuming that the power density profile in the radial direction of pellet remains to be the profile at the highest burnup recorded in the rodex file This is a good approximation because in high burn up region the power density profile has only a slight dependence on burnup extension
If the burnup of Re-start calculation exceeds markedly the upper bound recorded in rodex file of Base calculation the following convenient method is recommended In making rodex for Base calculation extend input irradiation history deliberately to attain much higher burnup than the EOL burnup of base irradiation After rodex is made eliminate the extended part of irradiation history of input file to perform Base calculation (2) Initial conditions of Re-start calculation If the segments for short re-fabricated rod are for example the 2nd to 5th segments of the full length rod by specifying ldquoIREST=5rdquo and ldquoTRSGT=2 5rdquo in the input file of test irradiation analysis the end-of-base-irradiation conditions of these segments ie sizes of pellet and cladding burnup profiles FGRs gap conditions etc are read from ft11 to be used as initial conditions of the analysis of fuel rod during test-irradiation Fig31 illustrates the relationship of rod segmentation for ldquoTRSGT=2 5rdquo
In this case plenum volume initial internal gas pressure and gas composition of test rod can be specified as a new set of initial conditions by name-list parameters in Re-start input file
Fig31 Axial segmentation of the full-length rod and re-fabricated short test-rod
Bottom Plenum re-fabricated zone
115mm 115mm 116mm Top segment 1
30mm Seg4 Seg3 Seg2
Full length rod
Short test rod
JAEA-DataCode 2013-009
- 29 -
as per usual Particularly the plenum volume has to be newly specified However values of initial gas pressure and gas composition are taken over from those in
ft11 if they are not newly specified by name-list parameters All the other conditions of fuel rod such as stress-strain of rod fission gas bubbles or accumulated amount of fission gas atoms power density profile in the radial direction of pellet etc are taken over from ft11
It is recommended that the formatted data of fuel rod specification (size shape) initial plenum volume initial internal pressure and gas composition in the input file of Re-start calculation be the same as those in the input file of Base calculation to circumvent misunderstanding As these data are read in Re-start calculation Re-start execution fails if they are not written in the input file However even if they are written they are not used as the initial values in Re-start calculation The initial values of these quantities in Re-start calculation are always fed by ft11 file
Here plenum volume internal gas pressure gas composition coolant conditions (equivalent diameter of flow area cross section area of flow fuel rod pitch) can be specified in input file as a new set of parameters for Re-start calculation (test irradiation) by using name-list parameters In this case the corresponding data stored in ft11 file are not used in calculation and quantities to be specified as initial conditions can be input by using some or all of the name-list parameters ITIME(n) GASPRN(n) GMIXN(n) DEN(n) FAREN(n) PITCHN(n) and PLENM(n) It is noted that when ITIME(n) is specified GASPRN(n) GMIXN(n) and PLENM(n) have to be specified invariably
All the other quantities such as stress-strain state of fuel rod conditions of fission gas bubbles and fission gas accumulation and power density in the radial direction of pellet are fed from ft11 file However either the data of power density profile vs burnup table which is attached at the last part of input file or the rodex file to be read by FEMAXI is always necessary in Re-start calculation
When IFEMRD=0 this Re-start calculation is also possible though the objective segment in which 2-D calculation is performed has to be the same segment that is specified by TRSGT If not error message is issued and calculation will not start
JAEA-DataCode 2013-009
- 30 -
333 Name-list parameters related to Re-start calculation
A group of name-list input parameters which are used in Re-start calculation function is
listed in Table 331
Table 331 Name-list parameters of FEMAXI-7 Restart function Parameter name Contents Default
Value
IREST
In FEMAXI-7 calculation (1) =0 Analysis only by FEMAXI-7
0
In FEMAXI-7 calculation (2) =4 generating Re-start file (ft11) for FEMAXI allowing the
designation of segments for refabricated short rod
In FEMAXI-7 Re-start calculation (3) =5 reading the restart file (ft11) generated by FEMAXI-7 to perform the FEMAXI calculation of test-irradiation for the axial segments designated by TRSGT However the objective segment for 2-D mechanical analysis in the base-irradiation calculation should be the same as the axial segment designated by TRSGT
TRSGT(2)
Input when IREST=5 in FEMAXI-7 Re-start calculation Otherwise error message is shown and calculation will start
Eg the number of segment is 10 in base-irradiation calculation and conditions of segments 4 to 6 are to be taken over TRSGT=46 is set If only 5th segment is the target TRSGT=5 is set
In performing the 2-D analysis designated objective segment No(specified by IFEM) has to be included in TRSGT For example in base-irradiation the objective segment is 5 (IFEM=5) and TRSGT=4 6 IFEM in Restart calculation is ldquoIFEM=2rdquo If this designation is inconsistent error message is shown and calculation will not start
0
IRTIME
When IRTIME=0 in the input file of Re-start calculation time (or burnup) has to be input as a sequential value from the beginning of base-irradiation
However if time is input burnup at EOL of base-irradiation calculation is taken over to be an initial burnup of Re-start calculation
When IRTIME=1 time at the start of Re-start calculation has to
be 0 and with this initial time=0 the Re-start irradiation history has to be given in input file However in Re-start calculation burnup at EOL of base-irradiation calculation is taken over and added to the initial burnup of Re-start input file
1
JAEA-DataCode 2013-009
- 31 -
334 Variables taken over and those not taken over in Re-start calculation
In performing Re-start calculation in FEMAXI-7 the following variables are taken over
from Base calculation to Re-start calculation They are explained in 6 groups classification
(1) Input variables given in fixed formats Variables given in fixed formats in input file of Base calculation are taken over to Re-start
calculation Accordingly fuel rod geometry except the designated axial segments is taken over
The other variables given in fixed formats eg coolant condition in the input file of Restart
calculation are also effective in Restart calculation Variables in fixed formats taken over in
Re-start calculation are listed in Table 332 Here the number of axial segments and IFEM
number for the objective segment are taken over as conditions of Base calculation to Re-start
calculation
Table 332 Variables in fixed formats taken over to Restart calculation
Name Content Name Content NAX Number of axial segments ENR U-235 enrichment (-) IFEM Number of objective segment FDENI Pellet theoretical density ratio (-)
MRASA Cladding material DZ Axial length of segment (cm) CDIN Cladding inner radius (cm) DISH Dish diameter (cm)
CDOUT Cladding outer radius (cm) DEPTH Dish depth (cm) IDISH Pellet dish specification DISHB Dish bottom circle diameter (cm) ICHAM Pellet chamfer specification PLENUM Plenum volume (cm3) PDIN Pellet center hole diameter (cm) GPIN Initial plenum gas pressure (MPa) PDIA Pellet diameter (cm) GMIXO Initial plenum gas composition (-)
PLENG Pellet length (cm) PWEIT Pellet total weight (g) CHAMR Chamfer width (cm) CHAMZ Chamfer depth (cm)
(2) Name-list input variables (parameters) Table 333 lists the name-list variables taken over from Base- to Re-start calculation 【Warning】 It is to be noted that if even one of these name-list variables (parameters) is
written in Re-start input file Re-start calculation never starts This is to circumvent the following situation if the same name-list variables as those used in Base calculation input file are explicitly written in Re-start input file with the different values from those in Base calculation or if some of the name-list variables are not written in Base calculation input file and are accepted as their default values in Base calculation while these name-list are explicitly written in Re-start input file with the different values from those in Base calculation
JAEA-DataCode 2013-009
- 32 -
FEMAXI neglects these values which are explicitly written in Re-start input file and takes over the values stored in Re-start file ft11 Here if users are not aware of this rule of Re-start calculation and have a false sense that Re-start calculation is performed with the parameter values written explicitly in Re-start input file the users will have inevitably a misunderstanding that the calculated results are obtained under the explicitly written values of parameters in Re-start input file This is a problem to be avoided so that the name-list input variables (parameters) listed in Table 333 must not be written in Re-start input file
Table 333 Name-list parameters and variables taken over from Base- to Restart calculation
(12) Name Content
PU PuO2 weight fraction (-) PUFIS Weight ratio of fissile Pu to total Pu(-)
AZ1 Ratio of length of element in the axial direction of half a pellet in the 2-D local mechanical analysis
ZR Zr-liner thickness (cm)
K1 Number of elements in the axial direction of half a pellet in the 2-D local mechanical analysis
ISHAPE Type of finite element used in the 2-D local mechanical analysis GD Gd2O3 concentration (wt fraction) DMAX Maximum fraction of volumetric shrinkage by densification () SBU Burnup of 90 completion of densification (MWdtUO2) TDNSF Pellet sintering temperature (K) GG Grain radius after heat treatment (m) GG0 Grain radius before heat treatment (m) SITIM Heat treatment time (hour) ADST Densification tuning factor A1 A1 in the swelling rate equation when IFSWEL=4 C1 C1 in the swelling rate equation when IFSWEL=4 BU1 BU1 in the swelling rate equation when IFSWEL=4 A2 A2 in the swelling rate equation when IFSWEL=4 SWSLD Factor to multiply the solid swelling rate 025 per 10E20 fissioncm3 RF Grain boundary gas bubble threshold radius (cm) FBCOV Fraction of grain boundary coverage by grain boundary lenticular gas bubbles CATEXF Axial growth factor fz in cladding irradiation growth equation COLDW Cladding cold work CW RX Multiplication factor for cladding irradiation growth rate GR Initial grain diameter of pellet (μm)
DD1 Adjustment factor for DMAX used in the merged model of densification and swelling
ALD Adjustment factor for α used in the merged model of densification and swelling
BU0 Baseline burnup used in the merged model of densification and swelling IFEMRD Option to activate 2-D local mechanical analysis
JAEA-DataCode 2013-009
- 33 -
Table 333 Name-list parameters and variables taken over from Base- to Restart calculation
(22) Name Content
LBU Option to use local burnup in burnup-dependent models MESH Option to select the number of pellet ring elements IDENSF Option to select pellet densification models IFSWEL Option to select pellet swelling models IGASP Option to select fission gas release model ICAGRW Option to select cladding irradiation growth model IRIM Option for additional FGR from high burnup structure DENSWL Option to activate the merged model of densification and swelling HBS Option to select the high burnup structure model RIMSWL Option for swelling model of high burnup structure NODEG Number of elements inside grain in fission gas diffusion model NODEH Number of elements inside grain in He gas diffusion model OXTH(IFEM) Initial oxide thickness of the objective segment (μm)
(3) Variables associated with the last stage of base irradiation (not name-list input parameters)
The variables which have the calculated values at the last stage of Base-irradiation are listed in Table 334
Table 334 Variables associated with the last stage of base irradiation Name Content
TIME Time (hour) PLHR Baseline linear power (Wcm) PCOOL Coolant pressure (Pa) FAI Fast neutron flux (ncm2s) FAIT Fast neutron fluence (ncm2) BUNP(NHIST) Baseline burnup (GJkgU)
(4) Variables taken over in thermal analysis (not name-list input parameters)
The variables which have the calculated values in thermal analysis at the last stage of Base-irradiation are listed in Table 335
Table 335 Variables of thermal analysis taken over to Restart calculation (15) Name Content
OXTHO Thickness of cladding outer oxide layer including plenum part (μm) OXTH2 Thickness of cladding inner oxide layer including plenum part (μm) CONCH Hydrogen concentration in cladding metallic part (ppm)
CONCO Hydrogen concentration at the previous time step in cladding metallic part (ppm)
JAEA-DataCode 2013-009
- 34 -
Table 335 Variables of thermal analysis taken over to Restart calculation (25) Name Content
IS Option to have a lower plenum NAX1 Number of segments in the axial direction of rod including plenum parts NPR Number of pellet ring elements in thermal analysis NRP Number of pellet ring elements in entire rod length mechanical analysis NC1 Number of cladding ring element nodes PIN Initial gas pressure in the plenum (Pa) GASPR Plenum gas pressure (Pa) PCOOLI Coolant initial pressure (Pa)
VTPLEN Value of plenum space volume divided by plenum gas temperature (cm3K)
XMOLO Initial number of moles of gas in plenum (mol) TOTMLO Number of moles of gas in plenum (mol) SUMHRS Number of moles of He (mol) SUMZRS Number of moles of fission gas (mol) FGRX Fission gas release rate () PLENLN Plenum length (cm) BU1 Average burnup over one segment (GJkgU) BR1F Local burnup (GJkgU) COLD Number density of atoms inside grain (at grain node) (atomscm3) BO Number of gas atoms in the grain boundary of one grain (atoms) TTALO Number of gas atoms inside grain (atoms) ABAR Radius of grain boundary gas bubble (cm) BBDEN Area number density of grain boundary gas bubbles (bubblesm2) AOLD Radius of intra-grain gas bubble (cm) ROLD Radius of FEM element node inside grain (cm) RLSD Amount of released fission gas atoms per one grain (atoms) GENED Amount of generated fission gas atoms per one grain (atoms) RFGRO FGR from high burnup structure (-) GRNS Pellet grain diameter (μm) BBLDO Number density of intra-grain gas bubbles (bubblescm3)
AMO Number density of fission gas atoms in intra-grain gas bubbles in pellet (atomscm3)
ABLD Number of grain boundary gas bubbles of one grain (bubblesgrain) TPOR Fission gas atoms density in the rim structure gas pore (atomscm3) RMPOR2 Gas pore swelling in the rim structure (-) TSWL Swelling by intra- and grain boundary gas bubbles (-)
BNMX Threshold number of area density of gas atoms in grain boundary (atomscm2)
BEFFO Effective burnup (GWdt) XV Rim transformation fraction in pellet (-) FPORE Fraction of fission gas atoms moved to rim gas pores (-) OPR Fraction of open porosity (-) RFGB Threshold radius of grain boundary bubble (cm)
P1 Internal pressure of intra-grain gas bubble and external pressure on the intra-grain bubble (dynecm2)
JAEA-DataCode 2013-009
- 35 -
Table 335 Variables of thermal analysis taken over to Restart calculation (35) Name Content
P2 Internal pressure of intra-grain gas bubble and external pressure on the grain boundary bubble (dynecm2)
TMDAT3(47) Volumetric strain induced by intra-grain gas bubbles () TMDAT3(49) Volumetric strain induced by grain boundary gas bubbles ()
TMDAT3(85) Number of generated fission gas atoms per unit volume of fuel (atomscm3)
TMDAT3(87) Number of generated fission gas atoms inside grain per unit volume of fuel grain (atomscm3)
TMDAT3(88) Number of generated fission gas atoms in intra-grain gas bubbles per unit volume of fuel (atomscm3)
TMDAT3(89) Number of intra-grain gas bubbles per unit volume of fuel (bubblescm3) TMDAT3(90) Number of fission gas atoms per unit area of grain boundary(atomscm2)
TMDAT3(91) Saturation (threshold) number of fission gas atoms per unit area of grain boundary (atomscm2)
TMDAT3(92) Number of gas bubbles per unit area of grain boundary (bubblescm2) TMDAT3(93) Covering fraction of grain boundary by grain boundary gas bubbles (-) TMDAT3(94) Saturation (threshold) radius of grain boundary gas bubbles (μm) RCII Initial inner radius of cladding (cm) RPOI Initial outer radius of pellet (cm) RPII Initial inner radius of pellet (cm) RCI Cladding inner radius (cm) RPO Outer radius of pellet (cm) RPI Inner radius of pellet (cm) TPSTG1 Pellet center temperature (K) CF Pellet-clad contact pressure (Pa) GAPI Initial gap width of pellet-clad (cm) GAP Pellet-clad gap width (cm) GAPO Pellet-clad gap width of previous time step (cm) GAPOO Array to store pellet-clad gap size data (cm) GHOT Pellet-clad gap width at hot stand-by (cm) TCSUF Temperature at the outer oxide surface of cladding (K) TPP1 Pellet temperature used in thermal analysis (K) TP1 Pellet temperature used in entire rod length mechanical analysis ((K) TC1 Cladding temperature (K) TCO Pellet center temperature at previous time step (K) TC Pellet center temperature (K) PGAS1 Amount of generated fission gas atoms (molcm) RGAS1 Amount of released fission gas (molcm) SIGM1 Pressure on grain boundary gas bubble (Pa) SIGA1 Pellet average internal stress (Pa) YS1 Pellet yield stress (Pa) GMIX Gap gas composition (-) GMIXO Initial gap gas composition (-) SOSW Solid swelling strain of pellet (-) URSW Gas bubble swelling strain of pellet (-) SUMSWO Radial displacement of pellet induced by swelling (cm)
JAEA-DataCode 2013-009
- 36 -
Table 335 Variables of thermal analysis taken over to Restart calculation (45) Name Content
SUMUSO Gas bubble swelling displacement of pellet at previous time step (cm) SUMUSW Gas bubble swelling displacement of pellet (cm) VGAP Space volume of P-C gap (cm3cm) VHOL Space volume of inner hole of pellet (cm3cm)
VFORM Space volumes associated with pellet shape such as dish chamfer pellet tilting etc (cm3cm)
SUMV Free space volume temperature inside fuel rod (cm3K) VOL Volume of active length part of fuel rod including internal space (m3) TPA Temperature of internal region of fuel rod (K) GMD Gas molar density at each axial segment (molm3) (=1He=2Xe) TMOL1 Molar number of gas at each axial segment (mol) (=1He=2Xe)
DZX Length of axial segment (cm) (including upper and lower plenum region)
POWER Linear heat rate (Wcm) AFIS Fission density (fissionscm3-s) AFAI Fast neutron flux (ncm2-s) AFAIT Fast neutron fluence (ncm2) TEMP Fuel( pellet cladding) temperature (K) PEX Displacement of pellet by thermal expansion (cm) PCR Displacement of pellet by creep (cm) PDN Displacement of pellet by densification (cm) PSW Displacement of pellet by swelling (cm) PRL Displacement of pellet by relocation (cm) PDS Total displacement of pellet (cm) CEX Displacement of cladding by thermal expansion (cm) CEL Elastic displacement of cladding (cm) CCR Creep displacement of cladding (cm) CDS Total displacement of cladding (cm) CFM Pellet-clad contact pressure (Pa) GAPX Pellet-clad gap width (cm)
PAS Displacement of pellet in the axial direction in the entire rod length mechanical analysis (cm)
CAS Displacement of cladding in the axial direction in the entire rod length mechanical analysis (cm)
SHFC Surface heat flux of cladding (Wcm2) SUCRP Creep displacement of pellet (cm) CCRP Creep strain displacement of cladding inner surface (cm) CCRPE Creep strain of cladding inner surface in the hoop direction (-) BD P-C bonding progress (hourMPa) BDO P-C bonding progress at previous time step (hourMPa) FDEN Pellet relative density (-)
ICLS Flag to indicate if the grain boundary bubble has made tunneling or not (=0tunneling =1not tunneling)
IGB Number of repetition of coalescence and closure of grain boundary bubbles when the bubbles make tunneling
RCIC Initial inner radius of cladding (cm)
JAEA-DataCode 2013-009
- 37 -
Table 335 Variables of thermal analysis taken over to Restart calculation (55) Name Content
RPIC Initial inner radius of pellet (cm) RPOC Initial outer radius of pellet (cm)
VCRC Relocation-induced space volume inside pellet at previous time step (cm3cm)
VCRCN Relocation-induced space volume inside pellet at current time step (cm3cm)
NPH Number of outermost element node for He release model FT Effective fluence of fast neutron (nm2) CW Cladding cold work (-) CTEMP Cladding temperature (K) RTEMP Cladding temperature changing rate (Ks) NPH Number of outermost mesh of fuel grain in He gas release model GASHE He gas partial pressure inside fuel rod (Pa) GASHEA He gas equilibrium pressure (Pa) TMLHE1 Molar number of He inside rod at previous time step (mol) TMLHE2 Molar number of He inside rod at current time step (mol) VOLHE Volume of He inside rod (cm3) HEDEN Concentration of He inside rod (atomscm3) RHOLD Nodal point radius inside grain for He diffusion calculation (cm) RHP Nodal coordinate values for He diffusion calculation (cm) HEOLD Number density of He in each nodal point inside grain (atomscm3) THALO Number of He atoms per one grain at previous time step (atoms) VOLM FEM element volume of pellet (cm3) GENEH Number of He atoms generated per one grain (atoms) DH0S Stored region of in-grain He diffusion coefficient (cm2s) DAH0S Stored region of in-grain He effective diffusion coefficient (cm2s) DBH0S Stored region of grain boundary He diffusion coefficient (cm2s) PGRH He generation rate at previous time step (atomscm3-s) PGRH2 He generation rate at current time step (atomscm3-s)
HEATM0 Initial numbers of generated He atoms in each ring element He atoms inside grain and He atoms at grain boundary (atoms)
HEATM Numbers of generated He atoms in each ring element He atoms inside grain and He atoms at grain boundary (atoms)
HEMOL0 Numbers of moles of generated He in each segment inside grain and at grain boundary at the beginning of time step (mol)
HEMOL1 Numbers of moles of generated He in each segment inside grain and at grain boundary at previous time step (mol)
HEGENE He generation density (atomscm3)
HEATMB Number of He atoms in the inside and outside regions of pellet at each segment (atoms)
HEATMB0 Initial number of He atoms in the inside and outside regions of pellet at each segment (atoms)
(5) Variables taken over in entire rod length (1-D) mechanical analysis (not name-list input parameters)
The variables which have the calculated values in the 1-D Entire Rod Length mechanical
JAEA-DataCode 2013-009
- 38 -
analysis at the last stage of Base-irradiation are listed in Table 336 Table 336 Variables taken over in ERL mechanical analysis (12)
Name Contents NR Number of elements in the radial direction of pellet and cladding KUNTS Counts of total time steps TEMPUO Upper plenum gas temperature at previous time step (K) TEMPLO Lower plenum gas temperature at previous time step (K) TBO Initial plenum gas temperature (K) TIMEOS Time at previous time step (hr) DTIMBS Time step increment at previous time step (hr) VS Fuel rod axial elongation (m) TEMPUS Upper plenum gas temperature at current time step (K) DTMPUS Upper plenum gas temperature increment (K) TEMPLS Lower plenum gas temperature at current time step (K) DTMPLS Lower plenum gas temperature increment (K) DTBOUS Difference between upper plenum gas temperature and room temperature (K) DTBOLS Difference between lower plenum gas temperature and room temperature (K) ALTSUS Thermal expansion strain of upper plenum spring (-) ALTCUS Thermal expansion strain of cladding of upper plenum (-) FWGZS Force imposed on the top end plane of upper plenum (N) FLZPS Force on lower plenum spring (N) FLZCS Force on cladding of lower plenum (N) FUZPS Upper plenum spring force (N) FUZCS Force on cladding of upper plenum (N) EPSR Relocation parameter EPSRR Relocation strain in the radial direction EPSRT Relocation strain in the circumferential direction PWEROS Linear heat rate (Wcm) BUS Segment average burnup (GJkgU) FISO Fission density (fisscm3-s) FAIS Fast neutron flux (ncm2-s) FAITS Fast neutron fluence (ncm2) DFAIS Fast neutron flux increment (ncm2-s) DFAITS Fast neutron fluence increment (ncm2) BR1S Local burnup (GJkgU) TEMPS Fuel temperature (K) DTEMPS Fuel temperature increment(K)
ICONTS P-C contact state(=0open gap =1pellet-clad bonded =2pellet-clad sliding =3 open gap but axial elongation is restricted by adjacent segment
FPRS P-C contact pressure (Pa) GAPS P-C gap width (cm) SWELS Swelling strain of pellet (-) EPSHTS Creep hardening strain at which Pughrsquos reversal occurs (-) EPSDNS Densification strain of pellet (-) PMS Direction of creep flow (=10tensile =00compressive)
IREVS In creep calculation of cladding =1 for adoption of Pughrsquos reversal =0 for non-adoption
JAEA-DataCode 2013-009
- 39 -
Table 336 Variables taken over in ERL mechanical analysis (22) Name Contents
SIGES Equivalent stress (Pa) SIGEBS Equivalent stress at previous time step (Pa) SIGYS Yield stress (Pa) EPSPS Equivalent plastic strain (-) EPSHPS Hot-pressing strain (-) EYNGS Youngrsquos modulus (Pa) EYNGBS Youngrsquos modulus at previous time step (Pa) US Node displacement (m) EPSTHS Thermal expansion strain (-) EPSCPS Creep strain at which Pughrsquos tensile reversal occurs (-) EPSCMS Creep strain at which Pughrsquos compressive reversal occurs (-) SIGS Stress (Pa) EPSCS Creep strain (-) EPSCBS Creep strain at previous time step (-) EPSHS Creep hardening strain (-) EPSS Total strain (-) EPSPVS Plastic strain (-) EPSES Elastic strain (-) EPSRLS Relocation strain (-) EPSDSS Densification + swelling strain (-) RS Ring element nodal coordinate value in the radial direction (m) IBD Flag to indicate P-C bonding state
(6) Variables taken over in 2-D local mechanical analysis when IFEMRD=0 (not name-list input parameters)
The variables which have the calculated values in the 2-D local mechanical analysis at the last stage of Base-irradiation are listed in Table 337 Table 337 Variables taken over in 2-D local mechanical analysis (12)
Name Content NOD2 Number of nodes NELM Number of elements NTEP Number of Gaussian points in the radial direction NRX Number of Gaussian points in the radial direction of pellet elements NRX1 NRX+1 ILOW Number of columns of Gaussian points in the radial direction ICOL Number of layers of Gaussian points in the axial direction NM Number of Gaussian points in the radial direction KL Number of Gaussian points in the axial direction I2 Number of pellet materials (UO2 and MOX) IFX Flag to indicate P-C contact state TEMP2 Temperature at Gaussian point in radial elements (K) EPSO2 Initial strain of element in the radial direction at Gaussian point (-) EPSTH Thermal strain in the radial direction at Gaussian point (-)
JAEA-DataCode 2013-009
- 40 -
Table 337 Variables taken over in 2-D local mechanical analysis (22) Name Content
EPSTA Thermal strain in the axial direction at Gaussian point (-) SMAX Swelling strain in the radial direction at Gaussian point (-) SWMAXI Swelling strain in the axial direction at Gaussian point (-) GRA1 Pellet grain size at Gaussian point (μm) CFU Pellet-clad contact pressure (Pa) CFV Pellet-clad frictional force in the axial direction (Pa) DELGP Pellet-clad radial gap size (cm) GAPGPX Distance between the contact pair of pellet and cladding (cm) SGN Direction of sliding VMU Frictional coefficient between pellet and cladding (-) NCNTB Table of variables of contact pairs composing gap element IALB Flag of contact state at pellet boundary NSO Contact state of the contact pair of pellet and cladding SBPON Contact force at the interface of one pellet and another (N) TU Nodal displacement (cm) XY0 Initial coordinates of nodal points (cm) EPSP Plastic strain of Gaussian point in the element (-) EPSE Elastic strain of Gaussian point in the element (-) EPSR Relocation strain of Gaussian point in the element (-) ZLOCA Information table of stressstrain etc at Gaussian points of elements IEP Flag to indicate elastic-plastic state (=0 elastic state =1plastic state) IRV YesNo flag of cladding creep reversal EPSRLI Initial relocation strains in the radial and circumferential directions of pellet (-) EPSRL Relocation strain of pellet at current time step (-) EPSGRS Upper limit of gas bubble swelling strain of pellet (-) ALC Coordinate value at the top of pellet when locking occurs (cm) EPSSWL Swelling strain of pellet (-) EPSSWS Solid swelling strain of pellet (-) EPSSWU Bubble gas swelling strain of pellet (-) EPSDEN Densification strain of pellet (-) EPSDNY Densification strain component of pellet (-) EPSSWY Swelling strain component of pellet (-) IPLIN Table of information to make shape map in 2-D mechanical analysis
IPELM Table of element number and its corresponding nodal number in 2-D mechanical analysis
JAEA-DataCode 2013-009
- 41 -
335 Explanations for sample Re-start calculations and method
(1) Explanation is given on the following Basic input data BBSd05 which is shown in
Table 338 Table 338 Basic input data set
BWR-type Rod BBS Case
ampINPUT IBUNP=1 IDAY=0 IRH=1 TROOM=2951 DTPL=00 ICORRO=3 PX=990
IPUGH=1 IFLX=-2 INPRD=2 RCORRO=4 DE=50 IRIM=1 RFGFAC=10
FRELOC=030 EPSRLZ=5D-3 IFSNT=2 IGRAIN=0 GR=64 GRWF=15
LBU=1 IPRO=0 R1=10 R2=10 ICAGRW=1 IHOT=1 BETAX=0002
ISPH=1 ICFL=1 IROD=0
ITIME(1)=10 GASPRN(1)=0641 PLENM(1)=8 GMIXN(11)=10 0 0 0
IFEMRD=0 IFEMOP=2 IDSELM=1 IDENSF=0 DMAX=520 FDENSF=0
IPEXT=14 IDCNST=1 AM1=4 IPTHCN=17 RF=5E-5 IFSWEL=1 A1=008
IBOND=0 IGAPCN=5 BDX=100000 ALBD=07 FBONDG=10 SBONDG=001
MAT3=2 FACT2=01 01 01 100 01 ICONV2=5 ICPLAS=2
ICHK=100 DDSIGE=100 CRPEQ=0 CRFAC=10 IPCRP=2 FCRFAC=10
IPTHEX=3 ATHEX=3561D-6 IRM=0 MESH=3 MOXP=0 IPLYG=1 IZYG=1
TCS=127315 IZOX=1 IST=1 ITEND=1 DDSIGE2=100 DLSIGE2=100 EFCOEF=01
IPRINT=11001 IPLOPT=1 DPBU=100
IWTHE=100190130 31 IWROD(1)=30 80 30 000100
ampEND
5 3
1 1285 1400
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 025 1264 1300 005078 0947 415
111 003 0
219 009 10 00 00 00 3677 00
119
00 01 2196E+13 51315 33 1 4
09853 10044 10044 10085 09974 8
24 3000 20E+13
3560 3000 20E+13
35601 220 1210E+13
65600 220 1210E+13
65601 1758 9669E+12
9997 1758 9669E+12
99971 0 6578E+12 51315 33 1 4
10000 0 0 29815 01 1 4
09853 10044 10044 10085 09974
1000120 0 0 29815 01 1 4
09853 10044 10044 10085 09974
1000140 2 15E+13 29815 72 1 4
1039 1026 1017 0986 0932 106
1007595 20 15E+13 56095 72 1 4
1039 1026 1017 0986 0932 3
1007600 0 15E+13 56095 72 1 4
1007610 0 15E+00 29815 01 1 0
STOP
JAEA-DataCode 2013-009
- 42 -
(2) Base-calculation data before Re-start calculation (BBSd05) As shown in Table 339 Base calculation data are composed by the irradiation history
data It is important to designate ldquoIREST=4rdquo This case is run with IFEMRD=0 which
designates the 2-D local PCMI analysis concurrently with the 1-D entire rod length
mechanical analysis When ldquoIFEMRD=0rdquo is taken over to Re-start calculation both 1-D and
2-D mechanical analyses are performed
In this case no designations are given to ITIME(1)=10 GASPRN(1)=0641
PLENM(1)=8 and GMIXN(11)=10 0 0 0 Execution with ldquoTable 339 filerdquo results in a Re-start file BBSd11
Table339 Base calculation input data before Restart calculation
BWR-type Rod BBS Case
ampINPUT IBUNP=1 IDAY=0 IRH=1 TROOM=2951 DTPL=00 ICORRO=3 PX=990
IPUGH=1 IFLX=-2 INPRD=2 RCORRO=4 DE=50
IRIM=1 RFGFAC=10 FRELOC=030 EPSRLZ=5D-3 IFSNT=2
IGRAIN=0 GR=64 GRWF=15 LBU=1 IPRO=0 R1=10 R2=10 ICAGRW=1
IHOT=1 BETAX=0002 ISPH=1 ICFL=1 IROD=0
IFEMRD=0 IFEMOP=2 IDSELM=1 IDENSF=0 DMAX=520 FDENSF=0
IPEXT=14 IDCNST=1 AM1=4 IPTHCN=17 RF=5E-5 IFSWEL=1 A1=008
IBOND=0 IGAPCN=5 BDX=100000 ALBD=07 FBONDG=10 SBONDG=001
MAT3=2 FACT2=01 01 01 100 01 ICONV2=5 ICPLAS=2
ICHK=100 DDSIGE=100
CRPEQ=0 CRFAC=10 IPCRP=2 FCRFAC=10 IPTHEX=3 ATHEX=3561D-6
IRM=0 MESH=3 MOXP=0 IPLYG=1 IZYG=1 TCS=127315 IZOX=1 IST=1
ITEND=1 IREST=4 DDSIGE2=100 DLSIGE2=100 EFCOEF=01
IPRINT=11001 IPLOPT=1 DPBU=100
IWTHE=100190130 31 IWROD(1)=30 80 30 000100
ampEND
5 3
1 1285 1400
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 025 1264 1300 005078 0947 415
111 003 0
219 009 10 00 00 00 3677 00
9
00 01 2196E+13 51315 33 1 4
09853 10044 10044 10085 09974 8
24 3000 20E+13
3560 3000 20E+13
35601 220 1210E+13
65600 220 1210E+13
65601 1758 9669E+12
9997 1758 9669E+12
99971 0 6578E+12 51315 33 1 4
10000 0 0 29815 01 1 4
09853 10044 10044 10085 09974
STOP
JAEA-DataCode 2013-009
- 43 -
(3) Sample test irradiation data in Re-start calculation A) A sample test irradiation data for Re-start calculation is shown in Table 3310 as BBSrd05 This case does not explicitly designates the 2-D mechanical analysis but performes both the 1-D and 2-D analyses It is important to set IRTIME=0 to perform Re-start calculation with continuous time from Base calculation At the beginning stage of Re-start calculation it is important to specify a new set of values of plenum volume gas pressure and gas composition ITIME(1)=1 GASPRN(1)=0641 PLENM(1)=8 and GMIXN(11)=10 0 0 0 Also it is important to set ldquoIREST=5rdquo to perform Re-start calculation In Table 3310 TRSGT=15 is set so that this is a normal Re-start calculation In other words number of axial segments is 5 which is identical to that of the Base calculation and performs calculation for axial segments 1 to 5
Table 3310 Test irradiation data for Restart calculation (BBSrd05)
BWR-type Rod BBS Case
ampINPUT IBUNP=1 IDAY=0 IRH=1 TROOM=2951 DTPL=00 ICORRO=3 PX=990
IPUGH=1 IFLX=-2 INPRD=2 RCORRO=4 DE=50
RFGFAC=10 FRELOC=030 EPSRLZ=5D-3 IFSNT=2
IGRAIN=0 GRWF=15 IPRO=0 R1=10 R2=10
IHOT=1 BETAX=0002 ISPH=1 ICFL=1 IROD=0
ITIME(1)=1 GASPRN(1)=0641 PLENM(1)=8 GMIXN(11)=10 0 0 0
IFEMOP=2 IDSELM=1 FDENSF=0
IPEXT=14 IDCNST=1 AM1=4 IPTHCN=17 A1=008
IBOND=0 IGAPCN=5 BDX=100000 ALBD=07 FBONDG=10 SBONDG=001
MAT3=2 FACT2=01 01 01 100 01 ICONV2=5 ICPLAS=2
ICHK=100 DDSIGE=100
CRPEQ=0 CRFAC=10 IPCRP=2 FCRFAC=10 IPTHEX=3 ATHEX=3561D-6
IRM=0 MOXP=0 IPLYG=1 IZYG=1 TCS=127315 IZOX=1 IST=1
ITEND=1 IREST=5 TRSGT=15 IWRES=0 IRTIME=0
DDSIGE2=100 DLSIGE2=100 EFCOEF=01
IPRINT=11001 IPLOPT=1 DPBU=100
IWTHE=100190130 31 IWROD(1)=30 80 30 000100
ampEND
5 3
1 1285 1400
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 025 1264 1300 005078 0947 415
111 003 0
219 009 10 00 00 00 3677 00
110
1000120 0 0 29815 01 1 4
09853 10044 10044 10085 09974
1000140 2 15E+13 29815 72 1 4
1039 1026 1017 0986 0932 106
1007595 20 15E+13 56095 72 1 4
1039 1026 1017 0986 0932 3
1007600 0 15E+13 56095 72 1 4
1007610 0 15E+00 29815 01 1 0
STOP
JAEA-DataCode 2013-009
- 44 -
B) Next an example having ldquoIRTIME=1rdquo is shown in Table 3311 as BSqd05 It is
important to set IRTIME=1 to perform Re-start calculation with a new time which starts at the
beginning of Re-start calculation Similarly to Table 3310 at the beginning stage of
Re-start calculation it is important to specify a new set of values of plenum volume gas
pressure and gas composition Also Re-start calculation requires IREST=5 In Table 3311
TRSGT=1 5 is set just like Table 3310 and a normal Re-start calculation is performed for
the segments 1 to 5
Table3311 Test irradiation data for Restart calculation (BSqd05)
BWR-type Rod BBS Case
ampINPUT IBUNP=1 IDAY=0 IRH=1 TROOM=2951 DTPL=00 ICORRO=3 PX=990
IPUGH=1 IFLX=-2 INPRD=2 RCORRO=4 DE=50
IRIM=1 RFGFAC=10 FRELOC=030 EPSRLZ=5D-3 IFSNT=2
IGRAIN=0 GRWF=15 IPRO=0 R1=10 R2=10
IHOT=1 BETAX=0002 ISPH=1 ICFL=1 IROD=0
ITIME(1)=1
GASPRN(1)=0641 PLENM(1)=8 GMIXN(11)=10 0 0 0
IFEMOP=2 IDSELM=1 FDENSF=0
IPEXT=14 IDCNST=1 AM1=4 IPTHCN=17 A1=008
IBOND=0 IGAPCN=5 BDX=100000 ALBD=07 FBONDG=10 SBONDG=001
MAT3=2 FACT2=01 01 01 100 01 ICONV2=5 ICPLAS=2
ICHK=100 DDSIGE=100
CRPEQ=0 CRFAC=10 IPCRP=2 FCRFAC=10 IPTHEX=3 ATHEX=3561D-6
IRM=0 MOXP=0 IPLYG=1 IZYG=1 TCS=127315 IZOX=1 IST=1
ITEND=1 IREST=5 TRSGT=15 IWRES=0 IRTIME=1
DDSIGE2=100 DLSIGE2=100 EFCOEF=01
IPRINT=11001 IPLOPT=1 DPBU=100
IWTHE=100190130 31 IWROD(1)=30 80 30 000100
ampEND
5 3
1 1285 1400
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 025 1264 1300 005078 0947 415
111 003 0
219 009 10 00 00 00 3677 00
110
120 0 0 29815 01 1 4
09853 10044 10044 10085 09974
140 2 15E+13 29815 72 1 4
1039 1026 1017 0986 0932 106
7595 20 15E+13 56095 72 1 4
1039 1026 1017 0986 0932 3
7600 0 15E+13 56095 72 1 4
7610 0 15E+00 29815 01 1 0
STOP
JAEA-DataCode 2013-009
- 45 -
C) Next an example of input data of Re-start calculation for a short segment rod is shown in
Tables 3312 Table 3312 is the case where the third segment is used as a short test rod In
this case ldquoIREST=5rdquo and ldquoTRSGT=3rdquo are specified in the input file of Re-start calculation
Since this specifies one axial segment geometry the input data is required to match the
one-segment geometry In line with this modification of relative distribution of linear power
in the axial direction is required Also change of the objective segment No (IFEM) is
required for the 2-D local mechanical analysis It is important that IFEM (=3) which has been
specified in Base calculation be included in the range of TRSGT Similarly to Table 3310 at
the beginning stage of Re-start calculation it is important to specify a new set of values of
plenum volume gas pressure and gas composition
Table3312 Test irradiation data for Restart calculation (IBBSud05)
BWR-type Rod BBS Case
ampINPUT IBUNP=1 IDAY=0 IRH=1 TROOM=2951 DTPL=00 ICORRO=3 PX=990
IPUGH=1 IFLX=-2 INPRD=2 RCORRO=4 DE=50
IRIM=1 RFGFAC=10 FRELOC=030 EPSRLZ=5D-3 IFSNT=2
IGRAIN=0 GRWF=15 IPRO=0 R1=10 R2=10
IHOT=1 BETAX=0002 ISPH=1 ICFL=1 IROD=0
ITIME(1)=1 GASPRN(1)=0641 PLENM(1)=2 GMIXN(11)=10 0 0 0
IFEMOP=2 IDSELM=1 FDENSF=0
IPEXT=14 IDCNST=1 AM1=4 IPTHCN=17 A1=008
IBOND=0 IGAPCN=5 BDX=100000 ALBD=07 FBONDG=10 SBONDG=001
MAT3=2 FACT2=01 01 01 100 01 ICONV2=5 ICPLAS=2
ICHK=100 DDSIGE=100
CRPEQ=0 CRFAC=10 IPCRP=2 FCRFAC=10 IPTHEX=3 ATHEX=3561D-6
IRM=0 MOXP=0 IPLYG=1 IZYG=1 TCS=127315 IZOX=1 IST=1
ITEND=1 IREST=5 TRSGT=3 IWRES=0 IRTIME=0
DDSIGE2=100 DLSIGE2=100 EFCOEF=01
IPRINT=11001 IPLOPT=1 DPBU=100
IWTHE=100190130 31 IWROD(1)=30 80 30 000100
ampEND
1 1
1 1285 1400
2 0 00 1264 1300 005078 0947 61625
111 003 0
219 009 10 00 00 00 00 00
110
1000120 0 0 29815 01 1 4
10044
1000140 2 15E+13 29815 72 1 4
1017 106
1007595 20 15E+13 56095 72 1 4
1017 3
1007600 0 15E+13 56095 72 1 4
1007610 0 15E+00 29815 01 1 0
STOP
JAEA-DataCode 2013-009
- 46 -
D) Next another example is shown in Table 3313 in which the 2nd 3rd and 4th segments are fabricated into a short test rod In this case ldquoIREST=5rdquo and ldquoTRSGT=2 4rdquo are set in the input file Accordingly this case has three axial-segment geometry so that the input data is required to match the three-segment geometry In line with this modification of relative distribution of linear power in the axial direction is required Also change of the objective segment No (IFEM) is required for the 2-D local mechanical analysis Specifically since the Base calculation has ldquoIFEM=3rdquo the Re-start calculation with IFEM=2 should be set because IFEM=3 denotes the second segment in TRSGT range ldquo2 3 4rdquo Similarly to Table 3310 at the beginning stage of Re-start calculation it is important to specify a new set of values of plenum volume gas pressure and gas composition
Table 3313 Test irradiation data for Restart calculation (BBSvd05)
BWR-type Rod BBS Case
ampINPUT IBUNP=1 IDAY=0 IRH=1 TROOM=2951 DTPL=00 ICORRO=3 PX=990
IPUGH=1 IFLX=-2 INPRD=2 RCORRO=4 DE=50
IRIM=1 RFGFAC=10 FRELOC=030 EPSRLZ=5D-3 IFSNT=2
IGRAIN=0 GRWF=15 IPRO=0 R1=10 R2=10
IHOT=1 BETAX=0002 ISPH=1 ICFL=1 IROD=0
ITIME(1)=1 GASPRN(1)=0641 PLENM(1)=5 GMIXN(11)=10 0 0 0
IFEMOP=2 IDSELM=1 FDENSF=0
IPEXT=14 IDCNST=1 AM1=4 IPTHCN=17 A1=008
IBOND=0 IGAPCN=5 BDX=100000 ALBD=07 FBONDG=10 SBONDG=001
MAT3=2 FACT2=01 01 01 100 01 ICONV2=5 ICPLAS=2
ICHK=100 DDSIGE=100
CRPEQ=0 CRFAC=10 IPCRP=2 FCRFAC=10 IPTHEX=3 ATHEX=3561D-6
IRM=0 MOXP=0 IPLYG=1 IZYG=1 TCS=127315 IZOX=1 IST=1
ITEND=1 IREST=5 TRSGT=24 IWRES=0 IRTIME=0
DDSIGE2=100 DLSIGE2=100 EFCOEF=01
IPRINT=11001 IPLOPT=1 DPBU=100
IWTHE=100190130 31 IWROD(1)=30 80 30 000100
ampEND
3 2
1 1285 1400
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
2 0 00 1264 1300 005078 0947 61625
111 003 0
219 009 10 00 00 00 00 00
110
1000120 0 0 29815 01 1 4
10044 10044 10085
1000140 2 15E+13 29815 72 1 4
1026 1017 0986 106
1007595 20 15E+13 56095 72 1 4
1026 1017 0986 3
1007600 0 15E+13 56095 72 1 4
1007610 0 15E+00 29815 01 1 0
STOP
JAEA-DataCode 2013-009
- 47 -
(4) Method to perform Re-start calculation The ft11 file taken over to Re-start calculation is generated in WrkOUTP as eg
AA1ft11 as a result of Base calculation with input file AAd05
If the input file name of Re-start calculation is BBd05 rename AA1ft11 into BBft11 and type after prompt ldquofem BB 1rdquo Then FEMAXI-7 reads BBft11 and BBd05
performs Re-start calculation and generates the output file BB1out
34 Usage of output of burning analysis code RODBURN-1 In FEMAXI to take into account the changes of some fission product elements and
power density profile of fuel pellet with burnup in the radial direction the burning analysis
code RODBURN-1 can be used as a pre-processing code Calculated results by
RODBURN-1 are compared with those of other burning analysis code in the later sections of
this manual indicating a reasonable predictability
Table 341 shows the output physical quantities and formats of RODBURN-1 which are
read by FEMAXI These data are output for all time steps between historical input points
designated in the input data to RODBURN-1 In FEMAXI linear interpolation is performed
with respect to burnup for these data obtained in each time step and the interpolated values
are used for calculations
Details of items in Table 341 are described below
341 Record No and contents
Record No 1 a heat generation density profile in the radial direction is an output at each
time step at the axial segment having maximum burnup It is assumed that changes in the
heat-generation density profile depend not on the axial position of a segment but only on
burnup Since the information on a segment with maximum burnup is output a table of
burnup vs radial heat-generation-density profile regarding the entire burnup regions
necessary can be produced after completion of the entire time step of RODBURN
Record No 2 number of axial segments is the number of divisions in the axial direction of a
fuel rod in RODBURN
Record No 3 average burnup and the amount of generated He of each axial segment are
output Record Nos 4 and 5 are used to modify history data for input data of
FEMAXI
JAEA-DataCode 2013-009
- 48 -
Record No 4 average burnup average linear heat rate and average fast neutron flux are
output
Record No 5 axial linear heat rate relative to average linear heat rate is output in order to
obtain linear heat rate and fast neutron flux of each axial segment
Record No 6 axial coordinates of each axial segment used in RODBURN
Table 341 Output variables and format of RODBURN-1 Record No
Data No Data Item Unit Format Column Note
1 1 2~11
Maxburnup Radial heat generation density profile
MWdt-U
F102 10F63
1~10 11~70 Refer to 1)
2 1 Number of axial segments I5 1~5
3
1 2~13
Average burnup Molar amount of He gas
MWdt-U Mole
F102 12E124
1~10 11~154
Refer to 1) Number of axial
segments
4
1 2 3
Average burnup Average linear heat rate
Fast neutron flux
MWdt-U Wcm
2ncm timess
F102 E124 E124
1~10 11~22 23~34
Refer to 1)
5 1~12 Axial relative power profile 12F63 1~72 Number of axial
segments
6 1~12 Axial coordinates cm 12E124 1~144 Number of axial
segments Refer to 2)
1) burnup of an axial segment 2) boundary coordinates between n-th and (n+1)th segment
342 Usage of records in FEMAXI To use data obtained from RODBURN-1 in FEMAXI the average linear power of a fuel
rod must be input into FEMAXI When the average linear power-input history is given the
average burnup at each historical point of input is calculated in FEMAXI by accumulating the
average linear power
The heat generation density profile in the radial direction in FEMAXI which is originally
calculated by RODBURN-1 can be obtained by interpolating the data with burnup in the
table of burnup vs heat generation density profile The data are prepared from the
RODBURN data group for the Record No1
JAEA-DataCode 2013-009
- 49 -
(1) Power density profile when MESH=0
In the case where pellet stack is divided into iso-volume ring elements in RODBURN-1
input the calculated results cannot directly correspond to the iso-thickness ring elements of
FEMAXI which has MESH=0 designation In this case the results of RODBURN-1 are used
in FEMAXI by volume interpolation or volume averaging
(2) Power density profile when MESH=1 2 3 or 4 (Recommended)
When MESHge1 the thermal analysis treats pellet stack as an assemblage of N=36 or
more iso-volume ring elements In this case RODBURN-1 sets N=36 or more ring elements
for pellet stack and sets the number of radial division of output file table as N
(3) Burnup profile of pellet in the radial direction
The burnup profile in the radial direction of a pellet stack obtained in RODBURN is not
forwarded to FEMAXI but an identical quantity can be obtained in FEMAXI by
accumulating the heat generation density profile over time The heat generation density is
given by a relative rate ie density ratio when the heat generation density averaged over all
the ring elements is set to 1 Accordingly assuming the density ratio of the i-th ring element in the radial direction to be Ri the burnup increment ∆Bui of this element is given by
∆ ∆Bu R Bui i= for the burnup increment ∆Bu of each time step for each segment The
burnup of each element can be obtained by integration of the burnup increment∆Bui over
time
(4) Molar amount of generated He
The molar amount of He gas is obtained in FEMAXI by interpolating the average burnup
data vs number of He moles generated with average burnup in the table which is produced
for each axial segment from the data group of the Record No 3
(5) Fast neutron flux
Among the historical data given in the input for FEMAXI the average fast neutron flux and
axial relative power ratio are corrected using data from the Record Nos4 and 5 These two
values in the axial direction are obtained by interpolating the following data with average
JAEA-DataCode 2013-009
- 50 -
burnup in FEMAXI (1) table of the average burnup vs average fast neutron flux and (2)
table of the average burnup vs relative power ratio in the axial direction both of which are
produced using data groups of the Record Nos 4 and 5
However sometimes differences happen to exist in the average linear heat rate
corresponding to the same average burnup between RODBURN output and FEMAXI input
data Therefore the difference in the average fast neutron flux is if exists corrected using
FEMFEM ROD
ROD
PP
φ φ= (A12)
and then used in FEMAXI
Here φFEM average fast neutron flux used in FEMAXI
φROD average fast neutron flux output from RODBURN
PFEM average linear heat rate input to FEMAXI
PROD average linear heat rate output from RODBURN
In order to deal with the differences if exist in the axial segment division between
RODBURN and FEMAXI a re-mesh function for the axial direction has been incorporated in
FEMAXI Namely putting a data value of the i-th segment in RODBURN as φi and that of
the (i+1)th segment as φi+1 and putting that of the j-th segment in FEMAXI as φjrsquo the axial
power profile is obtained by
( ) ( )
( )prime =minus prime + prime minus
prime minus primeminus +
minus
φφ φ
ji j i j i i
j j
Z Z Z Z
Z Z1 1
1
(A13)
and the molar amount of generated He gas is obtained by
( )( )
( )( )prime =
minus prime
minus+
prime minus
minusminus
minus ++φ φ φj
i j
i ii
j i
i ii
Z ZZ Z
Z ZZ Z
1
1 11 (A14)
Here Zi and Zj are the axial coordinates obtained from Record No 6 in RODBURN-1
and the axial coordinate in FEMAXI respectively
In RODBURN-1 pellet radius is divided into equal-volume ring elements in many cases
for the analysis of the power profile which is different from the equi-distance division by the
selection of MESH=0 Therefore the calculated values from RODBURN-1 are used by
interpolating with volume or by volume-averaging for the ring elements in FEMAXI
To avoid accumulation of errors due to the extension of burnup and interpolation
between axial coordinates a compensation processing is performed for obtained data
JAEA-DataCode 2013-009
- 51 -
343 Making input file of RODBURN-1 by using FEMAXI
In making an input file for RODBURN-1 prior to FEMAXI calculation an averaged
linear heat rate (LHR) values over representative history points are required However it is
often difficult to obtain directly the averaged LHRs from the data of time-LHR pairs or
burnup-LHR pairs of FEMAXI input file To solve this problem the following function has
been implemented in FEMAXI
First make your input file eg AAd05 of FEMAXI with IROD=1 if your rod is
PWR UO2 type If not IROD=2 3 4 or 5 in accordance with your reactor type and fuel type
Then execute FEMAXI The code will not run normally but automatically give rise to rodin
file in Wrk directory Rename rodin to AArddat and execute RODBURN
The rodin file has all that are needed to perform burning calculation of AA rod with
its history of axial distribution of linear power for every burnup stage When IRODge1 in its
input file FEMAXI calculates the linear heat rate at every axial segment along the irradiation
(burnup) history if the relative power profile data is given in FEMAXI input file for the axial
segments and generates a series of figures of linear heat rate history including the axial power
profile in ldquorodinrdquo file RODBURN utilizes this series of figures and average LHR value is
multiplied by relative axial power figure at each axial segment and burning calculation is
performed
After RODBURN calculation you have AArodex file in RODEX directory Then
modify IROD=1 to IROD=0 and put IFLX= -2 in your input file of FEMAXI Then you
can perform FEMAXI calculation with the RODBURN result
35 Usage of output of burning analysis code PLUTON By assigning name-list parameter IFLX=-1 it is possible to read the PLUTON
result file of burning calculation (refer to section 24) The FEMAXI readable file of
PLUTON can be generated as FMdat by PLUTON To feed this file into FEMAXI the file
is renamed into FMdt and stored in the directory Wrkrbout as described in section
A644 Regarding the details of the PLUTON code see the reference 24
JAEA-DataCode 2013-009
- 52 -
351 Physical quantities of PLUTON output for FEMAXI The following relationship describes the transfer of physical quantities from PLUTON to
FEMAXI
(1) Among the various calculation conditions in FEMAXI the quantities required to be
inputted to PLUTON are given below
Time Linear power distribution
Coolant water temperature Fuel composition
Void fraction of coolant water Diameter and inner diameter of the pellet
Pellet density Plant type
(2) The physical quantities read into FEMAXI among the outputs of PLUTON are given
below
Power distribution in the radial direction of the pellet
Fast-neutron flux
Burnup distribution in the radial direction of the pellet
Generated quantities of fission gas atoms Xe and Kr
352 Structure of inputoutput files of PLUTON (1) In the output files of PLUTON the average burnup average fast-neutron flux and power
density are normalized to a linear power of 100Wcm These files have a simple ASCII
format In the example shown in Table 351 lines are used to separate data In practice data
are separated by blank spaces
(2) The power density and Xe-Kr ratio are tabulated as functions of pellet radius
(3) These tables are output for each step of average burnup and various physical quantities at
the middle burnup at each step are determined by interpolating the values with burnup on the
FEMAXI side In addition in FEMAXI all the physical quantities are used by multiplying
the ratio of linear power for each segment by that for 100Wcm Tables for each burnup step
are continuous from the top to the bottom and two blank rows are used to separate each
burnup step
(4) The burnup range (BOL-EOL) and step burnup (∆B) are assigned at the input of
PLUTON The step width is small initially and becomes large in the high-burnup period
JAEA-DataCode 2013-009
- 53 -
(5) The naming convention used for output files in PLUTON is XXX-FEMdat For example
when the file name of PLUTON is BK365inp the output file name is BK365-FEMdat
Table 351 shows a simplified image of the output file format of PLUTON
- - - - - - - - Continues to the last table - - - - - - - - - - - - - - -
Table 351 Image of table structure of PLUTON
Av Burnup-1 (MWdt) 00 Fast flux-1 1564E13 (ncm2s)
Radii (mm) Power density-1 (Wcm3) XeKr Ratio 00 344E2 6875 0232 348E2 - - -
0328 - -
351E2 - - -
- - -
4639 411E2 - - -
4645 423E2 - - -
Av Burnup-1 (MWdt) 50000 Fast flux-1 1589E13 (ncm2s)
Radii (mm) Power density-1 (Wcm3) XeKr Ratio 00 344E2 6810 0232 350E2 - - -
0328 - - -
352E2 - - -
- - -
4639 428E2 - - - 4645 445E2 - - -
Av Burnup-1 (MWdt) 100000 Fast flux-1 1625E13 (ncm2s)
Radii (mm) Power density-1 (Wcm3) XeKr Ratio 00 344E2 6725 0232 351E2 - - - 0328 - - -
354E2 - - -
- - -
4639 452E2 - - - 4645 523E2 - - -
JAEA-DataCode 2013-009
- 54 -
In addition hereafter the detailed contents and format of the inputoutput files of
PLUTON are shown
【Example of Input file -1-】 Input parameters for the PLUTON code Physical Parameters ______________________________________________________________________________ List of variables Units Values ______________________________________________________________________________ FRDENS fractional fuel density na 0955 Bustep burnup power-step increment GWdt 020 Burnup upper burnup limit GWdt 600 EnriU5 initial enrichment with U-235 fraction 0045 CDiam1 the outer clad diameter cm 1430 CDiam2 the inner clad diameter cm 1267 FDiam1 the outer fuel diameter cm 1237 FDiam2 the inner fuel diameter cm 00 WEPITH 0304 - PWRUO2 0366 - PWRMOX 018 WWERUO2 0307 WFast 2010 - PWRUO2 2390 - PWRMOX 1514 TWater water temperature K 560 DWater water density at lower end plug gcc 0860 Vratio fuel to water ratio by volume NA 0627 VVoids void fraction NA 0350 TFuelC fuel temperature in resonant region C-degree 550 QLLBOL BOL reference LHGR wcm 2500 ______________________________________________________________________________ WtThor thorium content wt fraction fraction 00 ______________________________________________________________________________ ContPu plutonium content wt frac 0000 WtSPOT wt of Pu-spots in matrix wt frac 0000 SpDIAM average size of Pu-rich particles micron 500 SPOTU8 fraction of uranium in Pu-spots fraction 0750 PuFrac239 fraction of Pu-239 in total Pu fraction 0681 PuFrac240 fraction of Pu-240 in total Pu fraction 0218 PuFrac241 fraction of Pu-241 in total Pu fraction 0073 Pufrac242 fraction of Pu-242 in total Pu fraction 0028 ______________________________________________________________________________ ContGd content of Gadolinium Oxide Gd2O3 wt frac 0000 GdX154 fraction of Gd-154 isotope 213 GdX155 fraction of Gd-155 isotope 1461 GdX156 fraction of Gd-156 isotope 2034 GdX157 fraction of Gd-157 isotope 1565 GdX158 fraction of Gd-158 isotope 2500 GdX159 fraction of Gd-159 isotope 0000 GdX160 fraction of Gd-160 isotope 2227 ______________________________________________________________________________ NRADI number of points in radial mesh layout 101 NRADIF number of radial points in output power profile 25 iMeshF index of mesh point layout in output power profile -1 ifFEMF index of FEMAXI-readable output format 1 ifRESI 0 = classical formular gt 0 Egiazarovs formular 1 ifEDGE 0 for volume 1 - for rim region 0 iMeshL -1 iPlant =1 (PWR) =2 (BWR) =3 (HBWR) =4 (Riso DR3) 2 ifPLUT =0 local calculations gt 0 full-scale calculations 0 ifREIR =0 no re-irradiation ifREIR gt 0 if re-irradiation 0 ifDEPL Print out index for Xe amp Kr data 1 ifPOIS Print index for poisoning FP (C=1 W=2 Y=3) 1 inPOIS PuMOX index for poisoning FP (M=1 S=2 A=3) 1 ifCLAD Cladding type 2 iQUICK = 0 for quick succession gt 0 for full succession 0 iTRANS = 0 simple TUR-group gt 0 for full TUR-group 0 inTRUG Print index for TU-Group (M=1 S=2 A=3) 3 ______________________________________________________________________________ FLARCRP BWRRp60dat FLARCPU BWRBu60dat
JAEA-DataCode 2013-009
- 55 -
FLARCBU BWRPu60dat FLPOISS BWRPs60dat FLPOISR BWRPr60dat FEMFORM FEMAXI-readable format BWRFM60dat ______________________________________________________________________________ MODELOP default options ______________________________________________________________________________
【Example output file corresponding to the example input -1-】 --------------------------------------- ------------------------------- ------------------------------- ------ SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM RECORDS 0 1000 2000 3 FAST FLUX at LHGR = 100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s 0 1724E+13 1756E+13 1769E+13 3 SECTION AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO 0 6635 6675 6714 3 --------------------------------------- ------------------------------- ------------------------------ ------ 1 2 3 4 5 6 7 8 9 10 11 12 13 14 --------------------------------------- ------------------------------- ------------------------------ ------ Radius F-DENSITY BURNUP Xe_All Kr_All F-DENSITY BURNUP Xe-All Kr-All F-DENSITY BURNUP Xe-All Kr-All RECORDS relat Relative GWdtM Relative GWdtM Relative GWdtM 25 --------------------------------------- ------------------------------- ------------------------------ ------ 0141 0880 000 24776 3723 0874 087 24816 3698 0874 175 24858 3671 1 0245 0888 000 24775 3723 0882 088 24814 3698 0882 176 24857 3671 2 0316 0898 000 24773 3724 0893 089 24812 3699 0893 178 24855 3672 3 0374 0907 000 24771 3725 0902 090 24811 3700 0902 180 24853 3672 4 0424 0915 000 24769 3726 0911 091 24809 3700 0910 182 24852 3673 5 0469 0926 000 24767 3726 0922 092 24807 3701 0921 184 24851 3673 6 0510 0935 000 24766 3727 0931 093 24806 3702 0930 186 24849 3673 7 0548 0945 000 24764 3728 0941 094 24804 3702 0940 188 24848 3674 8 0583 0954 000 24762 3728 0951 095 24803 3703 0949 190 24847 3674 9 0616 0964 000 24761 3729 0961 096 24801 3703 0959 192 24845 3675 10 0648 0974 000 24759 3730 0971 097 24800 3704 0969 194 24844 3675 11 0678 0983 000 24757 3730 0981 098 24798 3704 0978 196 24843 3675 12 0707 0993 000 24756 3731 0991 099 24797 3705 0988 198 24842 3676 13 0735 1003 000 24754 3732 1001 100 24796 3705 0998 200 24841 3676 14 0762 1013 000 24753 3732 1012 101 24795 3706 1009 202 24841 3676 15 0787 1023 000 24752 3733 1022 102 24794 3706 1019 204 24840 3676 16 0812 1034 000 24750 3734 1033 103 24793 3706 1030 206 24841 3675 17 0837 1045 000 24749 3734 1045 104 24794 3706 1042 208 24842 3674 18 0860 1056 000 24749 3735 1057 106 24795 3706 1054 211 24845 3673 19 0883 1068 000 24748 3736 1070 107 24797 3705 1068 213 24851 3670 20 0906 1082 000 24748 3737 1085 108 24802 3703 1084 216 24860 3665 21 0927 1097 000 24750 3738 1103 110 24810 3700 1104 220 24877 3658 22 0949 1117 000 24753 3740 1127 112 24825 3694 1132 225 24904 3644 23 0970 1143 000 24759 3742 1161 115 24853 3684 1174 232 24955 3620 24 0990 1189 000 24773 3747 1226 121 24918 3658 1257 245 25066 3565 25 --------------------------------------- ------------------------------- ------------------------------- --------------------------------------- ------------------------------- ------------------------------- ----- SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM RECORDS 3000 4000 5000 3 FAST FLUX at LHGR = 100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s 0 1784E+13 1799E+13 1816E+13 3 SECTION AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO 0 6752 6790 6827 3 --------------------------------------- ------------------------------- ------------------------------- ----- 1 2 3 4 5 6 7 8 9 10 11 12 13 14 --------------------------------------- ------------------------------- ------------------------------ ------ Radius F-DENSITY BURNUP Xe_All Kr_All F-DENSITY BURNUP Xe-All Kr-All F-DENSITY BURNUP Xe-All Kr-All RECORDS relat Relative GWdtM Relative GWdtM Relative GWdtM 25 --------------------------------------- ------------------------------- ------------------------------ ------ 0141 0875 262 24898 3645 0875 349 24937 3619 0876 436 24975 3594 1 0245 0882 264 24897 3645 0883 352 24936 3619 0884 440 24974 3594 2 0316 0893 267 24896 3645 0893 356 24935 3619 0893 445 24973 3594 3 0374 0902 270 24894 3646 0902 360 24934 3620 0902 450 24972 3595 4 0424 0910 273 24893 3646 0910 363 24933 3620 0910 454 24971 3594 5 0469 0920 276 24892 3646 0920 367 24932 3620 0920 459 24970 3594 6 0510 0929 279 24891 3646 0929 371 24931 3620 0928 464 24969 3594 7 0548 0939 281 24890 3647 0938 375 24930 3620 0937 468 24968 3594 8 0583 0948 284 24889 3647 0947 379 24929 3620 0946 473 24968 3594 9 0616 0957 287 24887 3647 0956 383 24928 3620 0955 478 24967 3594 10
JAEA-DataCode 2013-009
- 56 -
0648 0967 290 24886 3647 0965 386 24927 3620 0964 482 24966 3594 11 0678 0976 293 24886 3647 0974 390 24926 3620 0973 487 24966 3594 12 0707 0986 296 24885 3647 0984 394 24926 3620 0982 492 24966 3594 13 0735 0996 299 24884 3647 0993 398 24926 3620 0991 497 24966 3593 14 0762 1006 302 24884 3647 1003 402 24926 3619 1001 502 24967 3592 15 0787 1016 305 24885 3647 1013 406 24927 3618 1011 507 24968 3591 16 0812 1027 309 24886 3646 1024 411 24930 3617 1021 513 24971 3589 17 0837 1039 312 24889 3644 1036 415 24934 3614 1033 518 24976 3586 18 0860 1051 316 24894 3641 1049 420 24940 3611 1046 525 24984 3581 19 0883 1066 320 24902 3637 1063 426 24951 3604 1061 532 24998 3573 20 0906 1083 324 24916 3629 1082 432 24969 3595 1080 540 25019 3561 21 0927 1105 330 24939 3617 1106 440 24998 3579 1106 550 25054 3542 22 0949 1136 338 24978 3597 1140 451 25047 3552 1144 565 25112 3509 23 0970 1185 349 25047 3561 1196 468 25133 3505 1206 588 25211 3453 24 0990 1286 372 25195 3482 1313 502 25309 3406 1338 634 25411 3336 25 --------------------------------------- ------------------------------- ------------------------------- ---- --------------------------------------- ------------------------------- ------------------------------ ------ SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM RECORDS 6000 7000 8000 3 FAST FLUX at LHGR = 100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s 0 1832E+13 1850E+13 1868E+13 3 SECTION AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO 0 6863 6899 6935 3 --------------------------------------- ------------------------------- ------------------------------ ------ 1 2 3 4 5 6 7 8 9 10 11 12 13 14 --------------------------------------- ------------------------------- ------------------------------ ------ Radius F-DENSITY BURNUP Xe_All Kr_All F-DENSITY BURNUP Xe-All Kr-All F-DENSITY BURNUP Xe-All Kr-All RECORDS relat Relative GWdtM Relative GWdtM Relative GWdtM 25 --------------------------------------- ------------------------------- ------------------------------ ------ 0141 0877 523 25011 3570 0878 611 25046 3547 0880 698 25080 3523 1 0245 0885 528 25010 3570 0886 616 25045 3546 0887 704 25079 3523 2 0316 0894 534 25009 3570 0895 623 25044 3546 0896 712 25078 3523 3 0374 0902 540 25008 3570 0903 629 25044 3546 0903 719 25078 3522 4 0424 0910 544 25008 3570 0910 635 25043 3546 0911 725 25078 3522 5 0469 0919 551 25007 3570 0919 642 25043 3545 0919 733 25077 3522 6 0510 0928 556 25006 3569 0928 648 25042 3545 0927 741 25077 3521 7 0548 0936 562 25006 3569 0936 655 25042 3545 0935 748 25076 3521 8 0583 0945 567 25005 3569 0944 661 25041 3545 0943 755 25076 3520 9 0616 0954 573 25004 3569 0952 667 25041 3544 0951 762 25076 3520 10 0648 0962 578 25004 3569 0961 674 25040 3544 0959 769 25075 3520 11 0678 0971 584 25004 3568 0969 680 25040 3543 0968 777 25075 3519 12 0707 0980 590 25004 3568 0978 687 25040 3543 0976 784 25076 3518 13 0735 0989 596 25004 3567 0987 694 25041 3542 0985 792 25077 3517 14 0762 0998 601 25005 3566 0996 701 25043 3540 0993 800 25079 3515 15 0787 1008 608 25008 3564 1005 708 25045 3538 1003 808 25082 3513 16 0812 1019 614 25011 3562 1016 715 25050 3535 1013 816 25087 3509 17 0837 1030 621 25017 3558 1027 723 25057 3531 1025 825 25095 3504 18 0860 1043 628 25027 3552 1041 732 25068 3524 1038 835 25107 3496 19 0883 1059 637 25042 3543 1057 742 25085 3513 1054 847 25127 3484 20 0906 1079 647 25067 3529 1078 755 25113 3497 1076 862 25157 3466 21 0927 1106 661 25107 3505 1107 771 25158 3470 1107 881 25206 3436 22 0949 1147 679 25173 3468 1151 794 25230 3428 1154 908 25285 3389 23 0970 1215 708 25284 3402 1224 830 25352 3354 1233 952 25416 3308 24 0990 1362 769 25503 3270 1385 906 25586 3209 1407 1045 25661 3151 25 --------------------------------------- ------------------------------- ------------------------------ ------ --------------------------------------- ------------------------------- ------------------------------ ------ SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM RECORDS 9000 10000 20000 3 FAST FLUX at LHGR = 100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s 0 1888E+13 1907E+13 2146E+13 3 SECTION AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO 0 6971 7005 7344 3 --------------------------------------- ------------------------------- ------------------------------ ------ 1 2 3 4 5 6 7 8 9 10 11 12 13 14 --------------------------------------- ------------------------------- ------------------------------ ------ Radius F-DENSITY BURNUP Xe_All Kr_All F-DENSITY BURNUP Xe-All Kr-All F-DENSITY BURNUP Xe-All Kr-All RECORDS relat Relative GWdtM Relative GWdtM Relative GWdtM 25 --------------------------------------- ------------------------------- ------------------------------ ------ 0141 0881 786 25113 3501 0883 873 25144 3478 0900 1757 25421 3261 1 0245 0888 792 25112 3500 0889 881 25144 3478 0904 1770 25422 3259 2 0316 0896 801 25112 3500 0897 890 25144 3477 0909 1786 25422 3257 3
JAEA-DataCode 2013-009
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0374 0904 809 25111 3499 0905 899 25143 3476 0914 1801 25422 3255 4 0424 0911 816 25111 3499 0911 906 25143 3476 0919 1814 25423 3253 5 0469 0920 825 25111 3498 0920 916 25143 3475 0924 1830 25424 3251 6 0510 0927 833 25110 3498 0927 925 25143 3474 0929 1845 25424 3249 7 0548 0935 841 25110 3497 0935 934 25143 3474 0933 1860 25425 3247 8 0583 0943 849 25110 3497 0942 942 25142 3473 0938 1874 25425 3245 9 0616 0950 857 25109 3496 0950 951 25142 3473 0943 1889 25425 3243 10 0648 0958 865 25109 3495 0957 960 25142 3472 0947 1904 25426 3241 11 0678 0966 873 25110 3495 0965 969 25143 3471 0952 1919 25428 3238 12 0707 0974 881 25110 3494 0972 978 25143 3469 0957 1934 25430 3235 13 0735 0983 890 25111 3492 0981 987 25145 3468 0963 1950 25433 3231 14 0762 0991 898 25114 3490 0989 996 25147 3466 0969 1967 25437 3226 15 0787 1000 907 25117 3488 0998 1006 25151 3463 0976 1985 25444 3220 16 0812 1010 917 25122 3484 1008 1017 25157 3458 0985 2004 25454 3212 17 0837 1022 927 25131 3478 1019 1028 25167 3452 0995 2027 25470 3200 18 0860 1035 938 25145 3469 1033 1041 25181 3442 1010 2053 25493 3182 19 0883 1052 952 25166 3456 1050 1056 25204 3428 1030 2087 25528 3157 20 0906 1075 969 25200 3435 1073 1075 25240 3405 1060 2133 25581 3119 21 0927 1107 991 25252 3403 1107 1101 25297 3370 1106 2198 25661 3063 22 0949 1156 1023 25337 3351 1159 1138 25386 3314 1180 2299 25779 2978 23 0970 1241 1075 25475 3263 1249 1199 25531 3220 1310 2470 25957 2848 24 0990 1427 1186 25731 3096 1446 1329 25794 3045 1590 2842 26235 2637 25 --------------------------------------- ------------------------------- ------------------------------ ------ --------------------------------------- ------------------------------- ------------------------------ ------ SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM RECORDS 30000 40000 50000 3 FAST FLUX at LHGR = 100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s 0 2456E+13 2830E+13 3243E+13 3 SECTION AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO 0 7681 8037 8419 3 --------------------------------------- ------------------------------- ------------------------------ ------ 1 2 3 4 5 6 7 8 9 10 11 12 13 14 --------------------------------------- ------------------------------- ------------------------------ ------ Radius F-DENSITY BURNUP Xe_All Kr_All F-DENSITY BURNUP Xe-All Kr-All F-DENSITY BURNUP Xe-All Kr-All RECORDS relat Relative GWdtM Relative GWdtM Relative GWdtM 25 --------------------------------------- ------------------------------- ------------------------------ ------ 0141 0915 2655 25644 3042 0926 3566 25845 2802 0930 4485 26034 2550 1 0245 0918 2671 25645 3039 0927 3583 25846 2797 0929 4502 26036 2545 2 0316 0920 2691 25646 3035 0927 3605 25848 2791 0929 4524 26040 2537 3 0374 0923 2710 25647 3031 0928 3624 25850 2786 0928 4543 26043 2530 4 0424 0925 2726 25649 3027 0929 3642 25852 2781 0928 4561 26045 2524 5 0469 0928 2747 25650 3023 0929 3664 25854 2775 0927 4583 26048 2517 6 0510 0930 2765 25651 3020 0930 3683 25856 2769 0926 4601 26051 2510 7 0548 0933 2782 25652 3016 0930 3702 25858 2764 0925 4620 26054 2503 8 0583 0935 2800 25653 3012 0930 3721 25860 2758 0924 4639 26057 2497 9 0616 0937 2818 25654 3009 0931 3741 25862 2753 0924 4658 26061 2489 10 0648 0939 2837 25656 3004 0931 3760 25865 2747 0924 4678 26065 2482 11 0678 0942 2856 25658 3000 0932 3781 25868 2740 0925 4699 26071 2473 12 0707 0945 2875 25661 2994 0934 3802 25873 2732 0926 4722 26078 2464 13 0735 0949 2895 25665 2988 0936 3825 25879 2724 0929 4748 26087 2454 14 0762 0953 2917 25672 2981 0940 3851 25887 2714 0933 4777 26099 2442 15 0787 0959 2941 25681 2971 0945 3880 25899 2702 0940 4812 26115 2428 16 0812 0966 2968 25694 2959 0953 3915 25915 2687 0951 4856 26136 2410 17 0837 0977 3001 25713 2943 0965 3959 25939 2667 0967 4913 26166 2387 18 0860 0993 3043 25742 2919 0983 4017 25972 2639 0991 4992 26206 2357 19 0883 1016 3099 25784 2887 1010 4098 26020 2602 1028 5105 26260 2319 20 0906 1052 3177 25846 2840 1053 4215 26087 2551 1083 5269 26333 2268 21 0927 1108 3292 25936 2772 1120 4391 26181 2481 1165 5520 26427 2203 22 0949 1199 3475 26064 2676 1227 4673 26309 2387 1286 5916 26548 2119 23 0970 1356 3790 26243 2540 1406 5154 26477 2261 1382 6557 26699 2016 24 0990 1679 4463 26501 2339 1682 6141 26706 2090 1527 7715 26888 1885 25 --------------------------------------- ------------------------------- ------------------------------ ------
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--------------------------------------- -------- SECTION-AVERAGE BURNUP MWdtM RECORDS 60000 1 FAST FLUX at LHGR = 100 Wcm ncm^2s 0 3637E+13 1 SECTION AVERAGE Xe-to-Kr RATIO 0 8822 1 --------------------------------------- -------- 1 2 3 4 5 6 --------------------------------------- -------- Radius F-DENSITY BURNUP Xe_All Kr_All RECORDS relat Relative GWdtM 25 --------------------------------------- -------- 0141 0930 5407 26213 2310 1 0245 0929 5423 26217 2303 2 0316 0928 5444 26221 2295 3 0374 0926 5463 26224 2288 4 0424 0925 5479 26227 2282 5 0469 0924 5499 26231 2274 6 0510 0923 5517 26234 2267 7 0548 0922 5535 26239 2260 8 0583 0922 5553 26243 2252 9 0616 0922 5572 26249 2245 10 0648 0923 5593 26256 2236 11 0678 0925 5615 26264 2227 12 0707 0928 5640 26274 2217 13 0735 0934 5669 26287 2206 14 0762 0941 5705 26303 2192 15 0787 0953 5749 26324 2177 16 0812 0970 5806 26352 2158 17 0837 0995 5884 26389 2134 18 0860 1027 5992 26435 2105 19 0883 1056 6145 26495 2069 20 0906 1092 6363 26571 2024 21 0927 1147 6680 26665 1968 22 0949 1226 7155 26775 1902 23 0970 1340 7893 26897 1827 24 0990 1513 9214 27028 1742 25 --------------------------------------- --------
JAEA-DataCode 2013-009
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【Example of input file -2-】 Inputs for FK-1 8x8BJ (Step I) Physical Parameters ______________________________________________________________________________ List of variables Units Values ______________________________________________________________________________ FRDENS fractional fuel density na 095 Bustep burnup power-step increment GWdt 020 Burnup burnup limit GWdt 4500 EnriU5 initial enrichment with U-235 fraction 0039 CDiam1 the outer clad diameter cm 1230 CDiam2 the inner clad diameter cm 1068 FDiam1 the outer fuel diameter cm 1044 FDiam2 the inner fuel diameter cm 000 WEPITH 0304 - PWRUO2 0366 - PWRMOX 018 WWERUO2 0307 WFast 2010 - PWRUO2 2390 - PWRMOX 1514 TWater water temperature K 560 DWater water density at lower end plug gcc 0860 Vratio fuel to water ratio by volume NA 0627 VVoids void fraction NA 0500 TFuelC fuel temperature in resonant region C-degree 550 QLLBOL BOL reference LHGR wcm 2300 ______________________________________________________________________________ WtThor thorium content wt fraction fraction 00 ______________________________________________________________________________ ContPu plutonium content wt frac 0000 WtSPOT wt of Pu-spots in matrix wt frac 0000 SpDIAM average size of Pu-rich particles micron 500 SPOTU8 fraction of uranium in Pu-spots fraction 0750 PuFrac239 fraction of Pu-239 in total Pu fraction 0681 PuFrac240 fraction of Pu-240 in total Pu fraction 0218 PuFrac241 fraction of Pu-241 in total Pu fraction 0073 Pufrac242 fraction of Pu-242 in total Pu fraction 0028 ______________________________________________________________________________ ContGd content of Gadolinium Oxide Gd2O3 wt frac 0000 GdX154 fraction of Gd-154 isotope 213 GdX155 fraction of Gd-155 isotope 1461 GdX156 fraction of Gd-156 isotope 2034 GdX157 fraction of Gd-157 isotope 1565 GdX158 fraction of Gd-158 isotope 2500 GdX159 fraction of Gd-159 isotope 0000 GdX160 fraction of Gd-160 isotope 2227 ______________________________________________________________________________ NRADI number of points in radial mesh layout 101 NRADIF number of radial points in output power profile 25 iMeshF index of mesh point layout in output power profile -1 ifFEMF index of FEMAXI-readable output format 1 ifRESI 0 = classical formular gt 0 Egiazarovs formular 1 ifEDGE 0 for volume 1 - for rim region 0 iMeshL -1 iPlant =1 (PWR) =2 (BWR) =3 (HBWR) =4 (Riso DR3) 2 ifPLUT =0 burnup calculations gt 0 TIME-POWER calculations 1 ifREIR =0 no re-irradiation ifREIR gt 0 if re-irradiation 0 ifDEPL Print out index for Xe amp Kr data 0 ifPOIS Print index for poisoning FP (C=1 W=2 Y=3) 0 inPOIS PuMOX index for poisoning FP (M=1 S=2 A=3) 0 ifCLAD Cladding type 2 iQUICK = 0 for quick succession gt 0 for full succession 0 iTRANS = 0 simple TUR-group gt 0 for full TUR-group 0 inTRUG Print index for TU-Group (M=1 S=2 A=3) 3 ______________________________________________________________________________ FLARCRP FK1_rpdat FLARCPU FK1_pudat FLARCBU FK1_budat FLPOISS FK1_Psdat FLPOISR FK1_Prdat FEMFORM FEMAXI-readable format FK1_FMdat ______________________________________________________________________________ MODELOP DEFAULT OPTIONS ______________________________________________________________________________
-Continues to next pagerarr
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Table 2 Design parameters FK-1 commercial base-irradiation ============================================================================== PARAMETER UNITS VALUES ______________________________________________________________________________ CLADmm Total Fuel Rod Length mm 39100 FUELmm Active Fuel Stack Length mm 38100 SYSMPa System pressure MPa 730 VELOCI Coolant velocity ms 252 DEPASS Passing diameter cm 1473 ACOREm Active core m 450 ifCLNT Index of Coolant (LW or HW) LW ifCIRC Index of Circulation (FC or NC) FC ------------------------------------------------------------------------------ NNODES Number of axial nodes in fuel rod representation 0 NCROSS Total number of specified cross-sections 0 ============================================================================== OUTPUT OPTIONS iMeshP Mesh poits layout in step-by-step output file -1 NMESHP Number of radial zones in step-by-step output file 25 iPRNTP Print out option for step-by-step output file On ============================================================================== RE-IRRADIATION OFF ============================================================================== Table 3 IRRADIATION HISTORY FK-1 ============================================================================= ns TIME | Linear Heat | Coolant | RES | FAST | REACTOR | Rate | temperature | factor | factor | index |----------------|---------------| | | iREIRR | QL Type | Inlet Delta | | | ----------------|----------------|---------------| | | [1]| EFPDs | Wcm | C - degree | | | ----------------------------------------------------------------------------- (1) (2) (3) (4) (5) (6) (7) (8) (9) ----------------------------------------------------------------------------- 0 0 20357 L 2780 80 0307 1514 0 1 377 20357 - - - - - 0 2 8651 20357 - - - - - 0 3 16926 20357 - - - - - 0 4 25200 20357 - - - - - 0 5 25536 22847 - - - - - 0 6 36457 22847 - - - - - 0 7 47378 22847 - - - - - 0 8 58300 22847 - - - - - 0 9 58656 21573 - - - - - 0 10 70704 21573 - - - - - 0 11 82752 21573 - - - - - 0 12 94800 21573 - - - - - 0 13 95235 17620 - - - - - 0 14 107190 17620 - - - - - 0 15 119145 17620 - - - - - 0 16 131100 17620 - - - - - 0 17 131487 19811 - - - - - 0 18 144191 19811 - - - - - 0 19 156895 19811 - - - - - 0 20 169600 19811 - - - - - 0 ============================================================================= ampstop ampStop ampSTOP
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【Output file corresponding to the input file -2-】 --------------------------------------- -------- SECTION-AVERAGE BURNUP MWdtM RECORDS 0 1 FAST FLUX at LHGR = 100 Wcm ncm^2s 0 2865E+13 1 SECTION AVERAGE Xe-to-Kr RATIO 0 6664 1 --------------------------------------- -------- 1 2 3 4 5 6 --------------------------------------- -------- Radius F-DENSITY BURNUP Xe_All Kr_All RECORDS relat Relative GWdtM 25 --------------------------------------- -------- 0141 0940 000 24771 3711 1 0245 0944 000 24771 3711 2 0316 0949 000 24770 3712 3 0374 0953 000 24769 3712 4 0424 0957 000 24768 3712 5 0469 0962 000 24767 3713 6 0510 0966 000 24766 3713 7 0548 0970 000 24765 3713 8 0583 0975 000 24764 3714 9 0616 0979 000 24764 3714 10 0648 0984 000 24763 3714 11 0678 0988 000 24762 3715 12 0707 0993 000 24761 3715 13 0735 0997 000 24761 3716 14 0762 1002 000 24760 3716 15 0787 1007 000 24759 3716 16 0812 1013 000 24759 3717 17 0837 1019 000 24759 3717 18 0860 1025 000 24759 3718 19 0883 1033 000 24760 3719 20 0906 1041 000 24761 3720 21 0927 1053 000 24764 3721 22 0949 1068 000 24768 3723 23 0970 1089 000 24776 3726 24 0990 1129 000 24791 3730 25 --------------------------------------- -------- --------------------------------------- -------- SECTION-AVERAGE BURNUP MWdtM RECORDS 2330 1 FAST FLUX at LHGR = 100 Wcm ncm^2s 0 2947E+13 1 SECTION AVERAGE Xe-to-Kr RATIO 0 6777 1 --------------------------------------- -------- 1 2 3 4 5 6 --------------------------------------- -------- Radius F-DENSITY BURNUP Xe_All Kr_All RECORDS relat Relative GWdtM 25 --------------------------------------- -------- 0141 0933 217 24897 3630 1 0245 0937 218 24897 3631 2 0316 0942 220 24896 3631 3 0374 0946 221 24895 3631 4 0424 0950 221 24895 3631 5 0469 0955 223 24894 3631 6 0510 0959 224 24893 3631 7 0548 0964 225 24893 3632 8 0583 0968 226 24892 3632 9 0616 0973 227 24892 3632 10 0648 0977 228 24892 3632 11 0678 0982 229 24891 3632 12 0707 0987 230 24891 3632 13 0735 0992 231 24892 3631 14 0762 0997 232 24893 3631 15 0787 1002 234 24894 3630 16 0812 1009 235 24897 3629 17 0837 1016 237 24901 3627 18 0860 1024 238 24907 3624 19 0883 1034 240 24916 3620 20 0906 1046 243 24930 3613 21 0927 1063 246 24951 3604 22 0949 1087 251 24983 3588 23 0970 1125 258 25037 3563 24 0990 1199 271 25144 3511 25 --------------------------------------- --------
Skipped to the last part rarr
JAEA-DataCode 2013-009
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--------------------------------------- -------- SECTION-AVERAGE BURNUP MWdtM RECORDS 42434 1 FAST FLUX at LHGR = 100 Wcm ncm^2s 0 4852E+13 1 SECTION AVERAGE Xe-to-Kr RATIO 0 8508 1 --------------------------------------- -------- 1 2 3 4 5 6 --------------------------------------- -------- Radius F-DENSITY BURNUP Xe_All Kr_All RECORDS relat Relative GWdtM 25 --------------------------------------- -------- 0141 0924 3902 26082 2521 1 0245 0925 3911 26084 2518 2 0316 0925 3921 26085 2515 3 0374 0925 3930 26085 2512 4 0424 0925 3937 26086 2509 5 0469 0925 3947 26087 2506 6 0510 0925 3956 26088 2503 7 0548 0926 3965 26090 2500 8 0583 0926 3976 26092 2496 9 0616 0927 3986 26094 2492 10 0648 0929 3998 26097 2488 11 0678 0931 4011 26101 2483 12 0707 0934 4026 26106 2477 13 0735 0938 4044 26114 2470 14 0762 0943 4065 26123 2461 15 0787 0951 4093 26136 2450 16 0812 0962 4128 26154 2436 17 0837 0978 4175 26178 2417 18 0860 1000 4240 26210 2393 19 0883 1031 4328 26252 2362 20 0906 1075 4454 26308 2320 21 0927 1139 4638 26382 2267 22 0949 1234 4914 26476 2198 23 0970 1379 5355 26598 2110 24 0990 1569 6183 26763 1991 25 --------------------------------------- -------- --------------------------------------- -------- SECTION-AVERAGE BURNUP MWdtM RECORDS 45764 1 FAST FLUX at LHGR = 100 Wcm ncm^2s 0 5054E+13 1 SECTION AVERAGE Xe-to-Kr RATIO 0 8656 1 --------------------------------------- -------- 1 2 3 4 5 6 --------------------------------------- -------- Radius F-DENSITY BURNUP Xe_All Kr_All RECORDS relat Relative GWdtM 25 --------------------------------------- -------- 0141 0923 4207 26144 2436 1 0245 0924 4215 26145 2433 2 0316 0924 4226 26146 2429 3 0374 0923 4235 26147 2426 4 0424 0923 4242 26148 2424 5 0469 0923 4252 26149 2420 6 0510 0924 4261 26150 2417 7 0548 0924 4271 26152 2414 8 0583 0925 4281 26154 2410 9 0616 0926 4292 26157 2406 10 0648 0927 4304 26160 2401 11 0678 0929 4318 26165 2396 12 0707 0932 4334 26170 2390 13 0735 0937 4353 26178 2383 14 0762 0943 4376 26188 2374 15 0787 0951 4407 26202 2363 16 0812 0963 4446 26220 2348 17 0837 0980 4499 26245 2330 18 0860 1003 4570 26278 2306 19 0883 1036 4670 26321 2275 20 0906 1083 4811 26377 2235 21 0927 1150 5015 26449 2184 22 0949 1248 5323 26541 2119 23 0970 1391 5812 26658 2037 24 0990 1499 6688 26816 1927 25 --------------------------------------- --------
JAEA-DataCode 2013-009
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353 Contents read by FEMAXI code
A handling method of physical quantities from PLUTON-PC read by FEMAXI is
explained
(1) Fast-neutron flux Since the value normalized to a linear power of 100Wcm is given as a function of
average burnup for fast neutrons the standard fast neutron flux is calculated using average
burnup and average linear power for each input time step and this result is given as the
fast-neutron flux for each input time step
(2) Radial power density distribution burnup distribution and generation of Xe-Kr These physical quantities represent the distributions in the radial direction of the pellet
the handling method differs depending on the pellet ring element number option (MESH) in
the thermal calculation of FEMAXI
A) When MESH=0
In this case the pellet is divided into 10 equal-volume ring elements Thus on the basis of
the output file table of PLUTON-PC (equal-volume element condition) the power density in
FEMAXI is calculated by multiplying the power density which is assigned to ring elements in
FEMAXI from the PLUTON-PC table by the ring volume of PLUTON-PC and by dividing
the result by the ring volume of FEMAXI See Fig351 and Table 352 When several
rings of PLUTON-PC correspond to the ring of FEMAXI the power density distribution is
calculated by volume-averaging each ring
1 2 3 4 5 6 7 8 9 10
1 2 3 4 5 6 7 8 9 10
11 12 13 14 15 16
Radial element of PLUTON
Radial element of FEMAXI (MESH=0)
Fig351 An example of calculating the power density profile for FEMAXI from PLUTON result when MESH=0 If plural ring elements of PLUTON correspond to one single ring element of FEMAXI averaging over the ring elements is performed to obtain the power density of one element in FEMAXI
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Table 352 An example of radial profile conversion from PLUTON to FEMAXI in the case of MESH=0 (Note When plural ring elements of PLUTON correspond to a ring of
FEMAXI volume-averaging is performed)
PLUTON FEMAXI 1 rarr 1 1 rarr 2
1 2 rarr 3 2 rarr 4 3 rarr 5
4 5 rarr 6 5 6 rarr 7
7 8 9 rarr 8 9 10 11 12 rarr 9
12 13 14 15 16 rarr 10
B) When MESH=1 In this case the pellet stack of each axial segment is divided into 100 equal-volume ring
elements Therefore it is necessary to set the number of divisions in the radial direction
NRADIF of the PLUTON output file table as 100 In examples 1 and 2 of the input files of
PLUTON NRADIF=25 is adopted to simplify the appearance of the output file
Here the burnup distribution calculated in PLUTON is not used in FEMAXI because the
power density distribution is passed onto FEMAXI However since the local burnup is
calculated from the power history and density distribution in the radial direction in FEMAXI
the burnup distribution in FEMAXI is essentially an identical one to that obtained by
PLUTON
C) When MESH≧1 (Recommended)
When MESHge1 the pellet stack of each segment is divided into N ie 36 or more
equal-volume ring elements Accordingly it is necessary to match the number of radial
division NRADIF of output table of PLUTON-PC to N+1 because PLUTON-PC outputs the
values at the boundary of ring elements To obtain the average value in each ring element
from these N+1 boundary values it is necessary to make an average of the two values at the
boundaries of each element This averaging calculation is done manually In the example
input files ndashEx1- and ndashEx2- for PLUTON-PC NRADIF=25 is set for simplicity of output
file image Here the burnup profile obtained by PLUTON-PC is not used in FEMAXI
because FEMAXI calculates the burnup profile internally by integrating the power density
JAEA-DataCode 2013-009
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profile fed from PLUTON-PC or other burning analysis code with time
354 Output file reading function of FEMAXI
It is important in the data reading processing in PLUTON to grasp the record numbers
written horizontally and the radial mesh numbers See Fig352 The horizontal record
number is determined by the value in column [A] The system reads the values encircled by
the mark as irec irec2 and irec3 from the left-hand side of column [A] The following is an
example for the case of three horizontal records
The program reads the section marked [A] into 120 columns and the locations marked by
correspond to columns 47 80 and 113 The value at each location is stored in variables irec
irec2 and irec3 respectively By the combination of these variables the number of records
written horizontally is determined When the combinations of irec irec2 and irec3 in the IF
statement are 1 0 0 0 2 0 and 0 0 3 the program is designed to read the record numbers 1
2 and 3 respectively
Upon the determination of horizontal record numbers the program reads the mesh number
in the radial direction of [B] stores it in variable imax and performs the reading process on
the basis of the number of meshes in the radial direction The data created by the process up to
this point is designated a group of data the process continues until the data is depleted --------------------------------------- ------------------------------- ------------------------------- --------
SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM RECORDS
0 1000 2000 3
FAST FLUX at LHGR = 100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s 0
1724E+13 1756E+13 1769E+13 3
SECTION AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO 0
6635 6675 6714 3
--------------------------------------- ------------------------------- ------------------------------- --------
1 2 3 4 5 6 7 8 9 10 11 12 13 14
--------------------------------------- ------------------------------- ------------------------------- --------
Radius F-DENSITY BURNUP Xe_All Kr_All F-DENSITY BURNUP Xe-All Kr-All F-DENSITY BURNUP Xe-All Kr-All RECORDS
relat Relative GWdtM Relative GWdtM Relative GWdtM 25
--------------------------------------- ------------------------------- ------------------------------- --------
0141 0880 000 24776 3723 0874 087 24816 3698 0874 175 24858 3671 1
0245 0888 000 24775 3723 0882 088 24814 3698 0882 176 24857 3671 2
0316 0898 000 24773 3724 0893 089 24812 3699 0893 178 24855 3672 3
0970 1143 000 24759 3742 1161 115 24853 3684 1174 232 24955 3620 24
0990 1189 000 24773 3747 1226 121 24918 3658 1257 245 25066 3565 25
--------------------------------------- ------------------------------- ------------------------------- --------
1 2 3
Fig352 Representative output image of PLUTON
larr[A]
larr[B]
JAEA-DataCode 2013-009
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Table 353 shows the variable read in the program Figures 353 and 354 show the
correspondence between the locations of variables read and the output of the reading program
Table 353 Variables under which PLUTON data are stored x is total number of data
Variables to be stored During writing 1 bu(100) bu(x) 2 irec irec(x) 3 hgr(100) lhgr(x)larrreal declaration 4 fflux(100) f_flux(x) 5 xekr_r(100) xekr_r(x) 6 imax imax 7 radr(100) rad_r(imax) 8 fdr(100100) fdr(ximax) 9 bur(100100) bur(ximax)
--------------------------------------- --------
SECTION-AVERAGE BURNUP MWdtM RECORDS
0 1
FAST FLUX at LHGR = 100 Wcm ncm^2s 0
2865E+13 1
SECTION AVERAGE Xe-to-Kr RATIO 0
6664 1
--------------------------------------- --------
1 2 3 4 5 6
--------------------------------------- --------
Radius F-DENSITY BURNUP Xe_All Kr_All RECORDS
relat Relative GWdtM 25
--------------------------------------- --------
0141 0940 000 24771 3711 1
0245 0944 000 24771 3711 2
0316 0949 000 24770 3712 3
0970 1089 000 24776 3726 24
0990 1129 000 24791 3730 25
--------------------------------------- --------
Fig353 Output image in the case where number of record in the lateral direction is 1
ibu(x)
irec
f_flux(x)
xekr_r(x)
imax
rad_r(imax) fdr(ximax)
bur(ximax)
lhgr_r(x)
imax lines
x is total number of data
N times repeated as one set of data
JAEA-DataCode 2013-009
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--------------------------------------- ------------------------------- ------------------------------- --------
SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM SECTION-AVERAGE BURNUP MWdtM RECORDS
0 1000 2000 3
FAST FLUX at LHGR = 100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s FLUX at QL =100 Wcm ncm^2s 0
1724E+13 1756E+13 1769E+13 3
SECTION AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO SECTION-AVERAGE Xe-to-Kr RATIO 0
6635 6675 6714 3
--------------------------------------- ------------------------------- ------------------------------- --------
1 2 3 4 5 6 7 8 9 10 11 12 13 14
--------------------------------------- ------------------------------- ------------------------------- --------
Radius F-DENSITY BURNUP Xe_All Kr_All F-DENSITY BURNUP Xe-All Kr-All F-DENSITY BURNUP Xe-All Kr-All RECORDS
relat Relative GWdtM Relative GWdtM Relative GWdtM 25
--------------------------------------- ------------------------------- ------------------------------- --------
0141 0880 000 24776 3723 0874 087 24816 3698 0874 175 24858 3671 1
0245 0888 000 24775 3723 0882 088 24814 3698 0882 176 24857 3671 2
0316 0898 000 24773 3724 0893 089 24812 3699 0893 178 24855 3672 3
0970 1143 000 24759 3742 1161 115 24853 3684 1174 232 24955 3620 24
0990 1189 000 24773 3747 1226 121 24918 3658 1257 245 25066 3565 25
--------------------------------------- ------------------------------- ------------------------------- --------
Fig
35
4(1
2)
O
utpu
t im
age
in th
e ca
se w
here
num
ber o
f rec
ord
in th
e la
tera
l dire
ctio
n is
3
ibu(
x)
lhgr
_r(x
)
f_flu
x(x
)
xekr
_r(x
)
fdr(
xim
ax)
bur
(x
imax
) ra
d_r(
imax
)
imax
irec3
imax
pie
ces
x is
tota
l num
ber o
f dat
a
irec2
ire
c
The
first
set
of
dat
a
JAEA-DataCode 2013-009
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--------------------------------------- --------
SECTION-AVERAGE BURNUP MWdtM RECORDS
60000 1
FAST FLUX at LHGR = 100 Wcm ncm^2s 0
3637E+13 1
SECTION AVERAGE Xe-to-Kr RATIO 0
8822 1
--------------------------------------- --------
1 2 3 4 5 6
--------------------------------------- --------
Radius F-DENSITY BURNUP Xe_All Kr_All RECORDS
relat Relative GWdtM 25
--------------------------------------- --------
0141 0930 5407 26213 2310 1
0245 0929 5423 26217 2303 2
0316 0928 5444 26221 2295 3
0970 1340 7893 26897 1827 24
0990 1513 9214 27028 1742 25
--------------------------------------- --------
Fig354 (22) Output image in the case where number of record in the lateral direction is 3
355 Unit conversion of burnup The unit of burnup is converted in FEMAXI as follows as required
(1) 1020 fissionscm3
Energy generated per fission 200 MeV 1020 fissionscm3=2x1028 eVcm3
Using 1 cm3=1096f (g) ftheoretical density ratio
1020 fissionscm3=1825x1027f eVg
Using 1 eV=1602x10-19 Joule 1020 fissionscm3=2924x108f Jouleg
Using 1 MWDtUO2=864x104JoulegUO2
1020 fissionscm3=3384x103f MWDtUO2
when f=095 1020 fissionscm3=3562x103 MWDtUO2
Using 1 MWDtUO2=11344 MWDtU
Finally 1020 fissionscm3=4040x103 MWDtU
n-th set of data
JAEA-DataCode 2013-009
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(2) Conversion between burnup rate FIMA and burnup
FIMA=(Number of fissionsnumber of atoms of initial heavy elements)
Here the number of atoms of the initial heavy elements denotes the total number of atoms
contained in the fuel such as [fertile isotopes 238U and 240Pu] and [fissile isotopes]
1 1 225 9375 FIMA at burnup MWh kgU MWd teU= minus cong cong
10 100 at burnup GWd tUminus cong
(3) Conversion of BU2 (GJkgU) to BUC (1020fissionscm3) using subroutine FSWELL
From eq (A) above 1020fissionscm3=2924x108f JoulegUO2
1020 fissionscm3=2924f JoulekgUO2
Using 1 JouleKgUO2=11344 JouleKgU
1020fissionscm3=3317f JoulekgUO2
Thus the conversion coefficient is 3317f
36 Calculation examples by RODBURN-1 and PLUTON To evaluate the predictability of the RODBURN-1 code it is necessary to compare the
calculated results with measured data of profiles of burnup or generated elements concentration
in the radial direction However this work has to overcome a tough task to obtain reliable
measured data of irradiated fuel Here allowing the work to be considered in a separate chance
a comparison of calculations between RODBURN-1 and PLUTON codes is carried out as a
simplified assessment Results of the PLUTON code have been relatively well validated with
measured data(3X)
361 PWR fuels (1) Calculation conditions As calculation conditions of UO2 and MOX fuels of PWR fuel specs and irradiation
conditions shown in Tables 361 and 362 are assumed In the calculations of RODBURN-1
and PLUTON size of fuel and major nuclear element composition are the same though the
coolant condition is different due to the code models However the coolant condition has no
significant difference and almost equivalent if it is specified by rod pitch=127mm in
RODBURN-1 or by fuelwater volume ratio=06 in PLUTON
JAEA-DataCode 2013-009
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Table 361 Conditions of sample calculation P-1R by RODBURN-1 UO2 MOX (PuO2 66 wt) Pellet diameter 82 mm
density 95 TD
Composition (enrichment)
235U = 4 238U = 96
235U =02 235U=998 239Pu=6534 240Pu=2368 241Pu=657 242Pu=349 236Pu=00 238Pu=091 243Pu=244Pu=245Pu=00
Cladding Outer diameter=97mm Inner diameter=84mm Burnup (GWdt) 0 about 85 GWdt Coolant condition Rod pitch = 127 mm
Table 362 Conditions of sample calculation P-1P by PLUTON UO2 MOX (PuO2 66 wt) Pellet diameter 82 mm
Density 95 TD
Composition (enrichment)
235U = 4 238U = 96
235U =2 235U=98 238Pu=11 239Pu=6534 240Pu=2368 241Pu=657 242Pu=349 236Pu=00 241Am=091 243Am=00
Cladding Outer diameter=97mm Inner diameter=84mm Burnup (GWdt) 0 about 85 GWdt Coolant condition FuelWater volume ratio = 06
(2) Calculated results
A) Results for PWR-UO2 fuel by RODBURN-1 calculation
Figs361 and 362 show respectively the profiles of relative power density and burnup of
UO2 fuel calculated by RODBURN-1 with burnup being a parameter In RODBURN-1
calculation is performed with a pellet which is divided into 36 iso-volume ring elements and
the calculated results corresponding to the half thickness position of each element are output
The symbols in the figure indicate the radial position of half thickness of ring elements In the
outer region of pellet relative power density is elevated with burnup due to Pu generation by
resonance absorption and fission of the generated Pu by thermal neutron Burnup is also
elevated in the outer region as a time-integral of power density
JAEA-DataCode 2013-009
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Fig362 Profiles of burnup of PWR-UO2 pellet calculated by RODBURN-1
B) Results for PWR-MOX fuel by RODBURN-1 calculation
Figs363 and 364 show the profiles of relative power density and burnup of MOX fuel
calculated by RODBURN-1 with burnup being a parameter
0 1 2 3 4
10
15
20
25
RODBURN-1 18 GWdt 180 508 856
Rela
tive
heat
genera
tion d
ensi
ty
Radius of UO2 pellet (mm)
0 1 2 3 4
0
50
100
150
200
RODBURN-1 18 GWdt 180 508 856
Radius of UO2 pellet (mm)
Burn
up
(G
Wd
t)
Fig361 Profiles of power density of PWR-UO2 pellet calculated by RODBURN-1
JAEA-DataCode 2013-009
- 72 -
Fig364 Profiles of burnup of PWR-MOX pellet calculated by RODBURN-1
In the case of MOX fuel power density profile in the early stage of irradiation has a
relatively appreciable depression in the central region in comparison with that of UO2 pellet
because resonance reaction by Pu is large in the peripheral region of pellet
0 1 2 3 4
10
15
20
25
Rela
tive
heat
genera
tion d
ensi
ty
Radius of MOX pellet (mm)
RODBURN-1 18 GWdt 178 492 822
0 1 2 3 4
0
50
100
150
Radius of MOX pellet (mm)
RODBURN-1 18 GWdt 178 492 822
Burn
up
(G
Wd
t)
Fig363 Profiles of power density of PWR-MOX pellet calculated by RODBURN-1
JAEA-DataCode 2013-009
- 73 -
C) Results for PWR-UO2 and MOX fuels by PLUTON calculation
Figs365 and 366 show respectively the profiles of relative power density and burnup of
UO2 fuel calculated by PLUTON with burnup being a parameter Figs367 and 368 show
respectively the profiles of relative power density and burnup of MOX fuel calculated by
PLUTON with burnup being a parameter In PLUTON burning calculation is performed with a
pellet which is divided into 36 nodes (boundary) iso-volume ring elements and the calculated
results corresponding to the node position are output The symbols in the figure indicate the
radial position of the node
By comparing the results of two codes for UO2 fuel (Figs361 and 365) it is found that
the peaking of power density profile in the outer region of pellet is larger in PLUTON in low
burnup period than in RODBURN while this relative magnitude is reversed in RODBURN in
high burnup
On the other hand by comparing the results of MOX fuel (Figs363 and 366) it is found
that the depression of power density in the outer region of pellet is particularly larger in
PLUTON in high burnup period than RODBURN
0 1 2 3 4
10
15
20
25
PLUTON 2 GWdt 20 50 85
Rela
tive
heat
gen
erat
ion
dens
ity
Radius of UO2 pellet (mm)Fig365 Profiles of power density of PWR- UO2 pellet calculated by PLUTON
JAEA-DataCode 2013-009
- 74 -
0 1 2 3 40
50
100
150
200 PLUTON
2 GWdt 20 50 85
Burn
up (
GW
dt)
Radius of UO2 pellet (mm)
0 1 2 3 4
10
15
20
PLUTON 2 GWdt 20 50 85
Rela
tive
heat
genera
tion d
ensi
ty
Radius of MOX pellet (mm)
0 1 2 3 40
50
100
150 PLUTON
2 GWdt 20 50 85
Burn
up (
GW
dt)
Radius of MOX pellet (mm)
Fig368 Profiles of burnup of PWR-MOX pellet calculated by PLUTON
Fig366 Profiles of burnup of PWR- UO2 pellet calculated by PLUTON
Fig367 Profiles of power density of PWR-MOX pellet calculated by PLUTON
JAEA-DataCode 2013-009
- 75 -
362 BWR fuels (1) Calculation conditions
As calculation conditions of UO2 and MOX fuels of BWR fuel specs and irradiation
conditions shown in Tables 363 and 364 are assumed Similarly to the calculations of WPR
fuels by RODBURN and PLUTON size of fuel and major nuclear element composition are the
same though the coolant condition is different due to the code models However the coolant
condition has no significant difference and almost equivalent if it is specified by rod
pitch=152mm in RODBURN or by fuelwater volume ratio=0627 in PLUTON
Table 364 Conditions of sample calculation by PLUTON UO2 MOX (PuO2 66 wt) Pellet diameter 948 mm
Density 95 TD
Composition (enrichment)
235U = 4 238U = 96
235U =2 235U=98 238Pu=11 239Pu=6534 240Pu=2368 241Pu=657 242Pu=349 236Pu=00 241Am=091 243Am=00
Cladding Outer diameter=1227mm inner diameter=1055mm Burnup (GWdt) 0 about 85 GWdt Coolant condition FuelWater volume ratio = 0627
Table 363 Conditions of sample calculation by RODBURN-1 UO2 MOX (PuO2 66 wt) Pellet diameter 948 mm
Density 95 TD
Composition (enrichment)
235U = 4 238U = 96
235U =02 235U=998 239Pu=6534 240Pu=2368 241Pu=657 242Pu=349 236Pu=00 238Pu=091 243Pu=244Pu=245Pu=00
Cladding Outer diameter=1227mm inner diameter=1055mm Burnup (GWdt) 0 about 85 GWdt Coolant condition Rod pitch = 152 mm
JAEA-DataCode 2013-009
- 76 -
(2) Calculated results
A) Result of the SWAT code
First a comparison is made between the results of RODBURN-1 and SWAT(31) Fig369
shows this comparison with respect to the relative power density profile at pellet average
burnup of 61 GWdt The results by the two codes have only a slight difference which suggest
that a simplified model of RODBURN-1 can give a satisfactory prediction in comparison with a
dedicated burning analysis code
B) Results for BWR-UO2 fuel by RODBURN-1 calculation
Figs3610 and 3611 show the profiles of relative power density and burnup of UO2 fuel
calculated by RODBURN-1 with burnup being a parameter In the outer region of pellet
relative power density is elevated with burnup due to Pu generation by resonance absorption
and fission of the generated Pu by thermal neutron Burnup is also elevated in the outer region
as a time-integral of power density
0 1 2 3 4 505
10
15
20
25 SWAT RODBURN-1
Rela
tive
Powe
r
Radius (mm)
FK series peaking profile 2004 June 8 (61GWdt)
Fig369 Comparison of power density profiles between the calculations of RODBURN-1 and SWAT
JAEA-DataCode 2013-009
- 77 -
C) Results for BWR-MOX fuel by RODBURN-1 calculation
Figs3612 and 3613 show respectively the profiles of relative power density and burnup
of BWR-MOX fuel calculated by RODBURN-1 with burnup being a parameter In the case of
MOX fuel power density profile in the early stage of irradiation has a relative depression in the
central region because resonance reaction by Pu is large in the peripheral region of pellet
00 01 02 03 04 05
10
15
20
25
RODBURN-1 19 GWdt 183 515 868
Rela
tive
heat
gen
erat
ion
dens
ity
Radius of UO2 pellet (mm)
0 1 2 3 4 5
0
50
100
150
200
RODBURN-1 19 GWdt 183 515 868
Radius of UO2 pellet (mm)
Burn
up
(GW
dt)
Fig3610 Profiles of power density of BWR-UO2 pellet calculated by RODBURN-1
Fig3611 Profiles of burnup of BWR-UO2 pellet calculated by RODBURN-1
JAEA-DataCode 2013-009
- 78 -
Fig3613 Profiles of burnup of BWR-MOX pellet calculated by RODBURN-1
D) Results for BWR-UO2 and MOX fuels by PLUTON calculation
Figs3614 and 3615 show respectively the profiles of relative power density and burnup
of UO2 fuel calculated by PLUTON with burnup being a parameter Figs3616 and 3617
show respectively the profiles of relative power density and burnup of MOX fuel calculated by
Fig3612 Profiles of power density of BWR-MOX pellet calculated by RODBURN-1
0 1 2 3 4 5
10
15
20
25
RODBURN-1 18 GWdt 180 499 831
Rela
tive
heat
gen
erat
ion
dens
ity
Radius of MOX pellet (mm)
0 1 2 3 4 5
0
50
100
150 RODBURN-1
19 GWdt 183 515 868
Burn
up
(GW
dt)
Radius of MOX pellet (mm)
JAEA-DataCode 2013-009
- 79 -
PLUTON with burnup being a parameter In PLUTON burning calculation is performed with a
pellet which is divided into 36 nodes iso-volume ring elements and the calculated results
corresponding to the node position are output The symbols in the figure indicate the radial
position of the node
By comparing the results of UO2 fuel (Fig3610 and 3614) it is found that the peaking
of power density profile in the outer region of pellet is larger in PLUTON in low burnup period
than in RODBURN while this relative magnitude is reversed in RODBURN in high burnup
On the other hand by comparing the results of MOX fuel (Figs3612 and 3616) the
depression in the outer region of pellet is particularly larger in PLUTON in high burnup period
than RODBURN
0 1 2 3 4 5
10
15
20
PLUTON 2 GWdt 20 50 85
Rela
tive
heat
gen
erat
ion
dens
ity
Radius of UO2 pellet (mm)
Fig3614 Profiles of power density of BWR-UO2 pellet calculated by PLUTON
JAEA-DataCode 2013-009
- 80 -
0 1 2 3 4 50
50
100
150 PLUTON 2 GWdt 20 50 85
Radius of UO2 pellet (mm)
Burn
up
(GW
dt)
0 1 2 3 4 5
10
15
20
PLUTON 2 GWdt 20 50 85
Rela
tive
heat
gen
erat
ion
dens
ity
Radius of MOX pellet (mm)
Fig3615 Profiles of burnup of BWR-UO2 pellet calculated by PLUTON
Fig3616 Profiles of power density of BWR-MOX pellet calculated by PLUTON
JAEA-DataCode 2013-009
- 81 -
Fig3617 Profiles of burnup of BWR-MOX pellet calculated by PLUTON
37 Usage of the Halden data-base TFDB
In Halden Project TEST-FUEL-DATA-BANK (TFDB) SYSTEM(32) has been produced
since 1985 and is available for utilizing the experimental data of HBWR Therefore a utility
program TF2FEM which processes TFDB data and generates irradiation history data applicable
to FEMAXI has been developed The major functions of TF2FEM include the following
It supports extraction of several hundred steps of records (history data points) representing
irradiation history from among a few hundred thousand records of TFDB
The extracted history data can be used as input history data for FEMAX
A data file to compare calculation results of FEMAXI with experimental data is also
produced from the TFDB data file
For details refer to TF2FEM Userrsquos Manual included in the code package
References 3 (31) KSuyama TIwasaki and NHirakawa Integrated Burnup Calculation Code System
SWAT JAERI-DataCode 97-047 (1997) [in Japanese] (32) Wiesenack W and Hustadnes V TEST-FUEL-DATA-BANK SYSTEM USER MANUAL
HWR-338 (1993)
0 1 2 3 4 50
50
100
150 PLUTON
2 GWdt 20 50 85
Burn
up
(GW
dt)
Radius of MOX pellet (mm)
JAEA-DataCode 2013-009
- 82 -
4 FEMAXI-7 Input manual
41 Explanation on the relationship of IS and IST
In the heat conduction calculation (thermal analysis) to reduce calculation time
steady-state mode and transient mode are interchanged depending on power conditions This
interchange is controlled by IS and IST which are further explained in sections 42 and 47
In sections 411 and 412 below detailed explanation about this method is given prior to the
entire description of input manual
411 Function of ISTATE value The steady-state mode uses a large time step increment while the transient mode uses a
sub-divided time step This time step size is controlled by an internal variable ISTATE The
ISTATE value is determined by the name-list parameters IS and IST and its function is
summarized in Table 41
Table 41 Function of ISTATE value IS is one of the options of heat conduction calculation and IST an option of internal gas
flow calculation ISTATE Function
0 Adoption of time stepΔt for steady-state mode with null specific heat
1 Adoption of time stepΔt for steady-state mode with null specific heat However Δt is sub-divided into a shorter one by the logics in gas flow calculation than the size of Δt when ISTATE=0
2 Adoption of time stepΔt for transient-state mode with non-zero specific heat Δt is further sub-divided in comparison with those when ISTATE=0 and 1
Here the steady-state mode calculation is to obtain a solution of temperature profile after
infinite length of time of fuel rod in the radial direction at each time step by assuming specific heat = 00 Namely by assuming Cv (volumetric specific heat[Jm3]) = 0 the heat conduction
equation Eq(411)
( ) ( ) ( ) ( ) ( ) [ ] vC T r T r t k T r T r t q r tt
partpart
= nabla sdotnabla + (411)
is transformed into
( ) ( ) ( )[ ] 0k T r T r t q r tnabla sdotnabla + = (412)
Solution of Eq(412) gives the steady-state temperature profile The purpose of this
method is to reduce calculation time by obtaining advantage from the fact that during a period
JAEA-DataCode 2013-009
- 83 -
of slow-changing power the steady-state solution makes a good approximation of the
temperature profile
On the other hand in the transient state calculation this steady-state approximation
cannot hold because rod power is varying with a significant magnitude Therefore Eq(411)
with non-zero specific heat is solved to obtain the temperature profile at each time step
412 Relationship between IS IST and ISTATE
IS and IST are independently determined variables Their values cannot be changed by
other input designations In the case of IS=0 2 3 and 4 the criteria to judge which one of 0
1 2 is set for ISTATE value is as follows
(1) ISTATE=2 is set when power change rate (up or down) exceeds 1Wcms
(2) When power change rate becomes less than 1Wcms and 100s elapses during the
period with ISTATE=2 ISTATE recovers to either ISTATE=0 or =1 in accordance
with the IST value See Table 42
(3) However the transient state addressed in (1) and (2) is induced solely by power
change It does not take into consideration of another type of transient state in which
fuel rod temperature is varied by the change of coolant flow rate
(4) When IS=3 or 4 since the boundary condition of heat conduction equation is the
input-specified temperature of cladding outer surface thermal hydraulic calculation of
coolant is usually not performed (IS3P=0(default) no calculation of thermal
hydraulics of coolant)
Table 42 Set values of ISTATE
IS IST
0 1 2 3 0 1 or 2 0 or 2 0 or 2 0 or 2 2 2 2 2 2
3 4 1 or 2 0 or 2 0 or 2 0 or 2
413 Options specified by IS and IST
IS an option parameter for heat conduction calculation IS = 0 steady-state calculation is performed with 0vC = No sub-division of time step size
is done = 2 transient state calculation is performed with 0vC gt Sub-division of time step size is
JAEA-DataCode 2013-009
- 84 -
automatically done depending on the power change
= 3 condition of fixed temperature at cladding outer surface
= 4 condition of fixed temperature at cladding outer surface
Note (1) IS=3 is the same option as IS=4 In the case in which input cladding temperature is not
varied from the preceding history point of input written in input file IS=4 can be input
to omit the line No13 in input file
(2) When IS is not specified in input file IS=0 is automaticaslly set as default value
(3) When IS is either 3 or 4 procedure for the specific heat and time step size ie setting
of ISTATE value follows Table 42
IST option for internal gas flow default is IST=1 =0 model of gas diffusion in the axial direction is applied
Calculation is performed to have an instantaneous equilibrium of pressure inside rod
within each time step by assuming instantaneous movement of gas the amount of which is
proportional to the fission gas fraction in total gas amount However since the gas
compision varies in every axial segment diffusion calculation among the segments is
concurrently done to attain an uniform composition distribution with time through several
time steps
=1 model of instantaneous pressure equilibrium and complete mixture of gas
Calculation of transferred amount of gas is performed to obtain an instantaneous
complete mixture of composition and pressure equilibrium as well inside fuel rod ie in
every axial segment and plenum
=3 model of gas isolation in each segment
After the instant when either the Pellet-Clad contact pressure exceeds GPCPR (MPa)
or BD which is the bonding progress factor exceeds BDTR (input specified value) in at
least one axial segments gas transfer in the axial direction is not taken into account and
calculation of gas release and pressure is performed independently in each segment In
other words neither pressure equilibrium nor diffusion of gas species are considered
among the axial segments as if each segment were isolated with respect to internal gas
However in the segment which is adjacent to the plenum pressure calculation is
done by taking account of the space volume and gas temperature in the plenum
In the cases other than the above situations the model of instantaneous pressure
JAEA-DataCode 2013-009
- 85 -
equilibrium and complete mixture of gas (IST=1) is applied 42 Fixed format input (1)
Line No SYMBOL (FORMAT)
1 MTITL(I) I=1 20 (20A4) Free title Free title can be input in 2th to 80th columns
2
yenINPUT Calculation conditions are designated by Name-list parameters
(2~80 columns) in between ldquoyenINPUTrdquo and ldquoENDrdquo yenEND
3
NAX IFEM (2I10) Fuel rod specifications NAX = number of axial segments (1leNAXle40) IFEM = the objective segment number (1 le IFEM1 le NAX) I=1bottom of rod I=NAX top
4 MRASA CDIN CDOUT (I10 2F100) Cladding specifications
MRASA = 0 helliphellip RA material = 1 helliphellip SR material CDIN = cladding inner diameter (cm) CDOUT = cladding outer diameter (cm)
5
The number of NAX required (I = 1 NAX) IDISH(I) ICHAM(I) PDIN(I) PDIA(I) PLENG(I) ENR(I) FDENI(I) DZ(I) (2I10 6F100)
Pellet specifications
Number of ring elements of pellet is selected by MESH
IDISH(I) = 0 helliphellip pellet without dish = 1 helliphellip pellet with dish on only one end face = 2 helliphellip pellet with one dish each end face ICHAM(I) = 0 helliphellip pellet without chamfer = 1 helliphellip pellet with chamfer PDIN (I) = pellet center hole diameter (cm) PDIA (I) = pellet diameter (cm) PLENG(I) = length of one pellet (cm) ENR (I) = U-235 enrichment (minus) FDENI(I) = pellet theoretical density ratio (minus)
DZ (I) = axial segment length of pellet stack part (cm)
6
Input only when IDISH = 1 or 2 DISH DEPTH DISHB (3F100) Dish specifications
DISH = dish diameter (cm) DEPTH = dish depth (cm) DISHB = dish bottom diameter (cm)
7 Input only when ICHAM = 1
CHAMR CHAMZ (2F100) Chamfer specifications
CHAMR = chamfer width (cm) CHAMZ = chamfer depth (cm)
8
PLENUM(2) GPIN (GMIXO(I) I=14) PWEIT PLENUM(1) (8F100) Plenum specifications
PLENUM(2) = upper plenum volume (cm3) GPIN= initial gas pressure (MPa) GMIXO(I) = initial gas composition (minus) i = 1hellipHe i = 2hellipN2 i = 3hellipKr i = 4hellipXe PWEIT = pellet total weight (g)
When the input value is 80 - 100TD of that calculated in the code burnup is calculated using the input value If the input value exceeds this range Error Stop occurs When it is blank the value is automatically calculated
PLENUM(1) = lower plenum volume (cm3)
JAEA-DataCode 2013-009
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Fixed format input (2)
Line No SYMBOL (FORMAT)
9 NHIST (I10) Number of history
point Input NHIST (1ltNHIST le 1500) NHIST sets consisting of Lines 101112 and 13 are input
10
A1 B1 A2 A5 A3 A4 IT IP IS A6 (6F1003I5F50) History point data
A1 = time (IDAY=0hour =1day)
B1 = burnup (MWdtUO2 (IBUNP=0) MWdtU (IBUNP =1) GJkgU (IBUNP =2) GWd tUO2 (IBUNP=3)
Here either A1 (time) or B1 (burnup) should be designated If both are designated B1 is neglected
A2 = linear heat rate (Wcm)
A5 = fast neutron flux (ncm2-s) If no data or 0 are input the flux follows IFSINP A3 = coolant temperature (K) A4 = coolant pressure (MPa)
IT = 0 time (or burnup) represents the increment from the time step set at
IT=minus100 (when IT= -100 is not set it represents the time (or burnup)
elapsed from the initial time) = -100 time increment from the previous time step (or burnup increment) = 100 cancellation of the IT= -100 setting (time or burnup represents the
time (or burnup) that elapsed from the initial time)
IP = 0 history point without summary output = 1 history point with summary output IS = 0 steady-state calculation
= 2 transient state calculation = 3 condition of fixed temperature at cladding outer surface = 4 the same as IS=3 but input file format can be varied slightly
A6 = coolant velocity (ms) (ICLMAS=0) = coolant mass flow rate (kgcm2s) (ICLMAS=1)
Note If the initial values for A3 A4 and A6 are inputted they need not be inputted thereafter
JAEA-DataCode 2013-009
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Fixed format input (3) Line No SYMBOL (FORMAT)
11
(RH(I) I=1 NAX) II ((8F80) 8F80 I6) Relative power profile in the axial direction
RH(I) = relative power of axial segment j (minus) (number of data NAX) II = number of history points at which similar relative power is input When II is designated as 2 or higher Line 11 is omitted for the input of later time step
II-1
When more than 2 values of II are inputted card 11 is omitted for the input of time step
II-1 thereafter In addition when II= 1 the output to II can be omitted
(II can be assigned starting from the right-hand side of each column between the 65th
column to the 70th column of the last card)
12
(RFAI(I) I=1 NAX) II ((8F80) 8F80 I6) Relative fast neutron flux in the axial direction
Input this line only when IRFAI=1 in Name-list Input is designated RFAI(I)=relative fast neutron flux at the axial segment I (-)
(NAX data values) NAX8 cards (rounded up) are required
II = the number of historical points for inputting identical fast- neutron fluxes
Here when more than two values are assigned to II thereafter line 12 is omitted
for the input of time steps of II-1 Furthermore when II=1 the input to II can be
omitted (II is assigned starting from the right-hand side of each column between the
65th column to the 70th column of the last line)
13
(CSTMP(I) I=1 NAX) (8F80) Cladding outer surface temperature
Input only when IS=3 in Line 10 CSTMP(I)=cladding outer surface temperature (K) at the axial segment I
(NAX data values) NAX8 cards (rounded up) are required Refer to ICTP and ICSTMP
14
BU (RRH(I) I=1 NP) ( F100 10F60 (10X 10F60) ) Relative power density profile in the radial direction
Input only when IFLXgt0 BU = burnup (unit is similar to that in Line 10)
BU = burnup (MWdtUO2 (IBUNP=0) MWdtU (IBUNP =1) GJkgU (IBUNP =2) GWd tUO2 (IBUNP=3) ) RRH(I) = power density profile of concentric ring element I
(arbitrary unit normalized by FEMAXI ) or =[power density in element I][pellet average power density] The input line number is designated by IFLX in NAMELIST When IFLXM=0 NP=10 number of iso-thickness ring elements
When IFLXM=1 NP=number of ring elements of pellet stack specified by MESH
15 IEND (A4) Input end line Input ldquoSTOPrdquo
JAEA-DataCode 2013-009
- 88 -
43 Name-list Input (1) Variable name Contents Default
value
Input options IBUNP Designation of unit of burnup (=0MWdtUO2 =1MWdt-U
=2GJkg-U =3GWdtUO2) 0
IDAY Unit of time for input history points (=0hr=1day) 0
ISEC(2 5)
During the period ISEC(1I) - ISEC(2I) time unit is changed to be second ISEC(1I) is the number of history point at which the change starts and ISEC(2I) is the number of history point at which the change ends The maximum number of the periods is five
100
IFLX
Number of power history points to designate the radial power profile If the numerical data are not given IFLX should be one of 0 -1 o -2 which corresponds to the following options = 0 Robertson model -1PLUTON results -2 RODBURN results
ge 1 number of burnup points at which the radial profile data are specified
When IFLX= -1 or -2 corresponding results files should exist in the WrkRBOUT Here when IFLX= -1 (fed from PLUTON file) the output file ldquoft51drdquo of PLUTON should be prepared in advance
0
IFLXM Option to specify the number of ring elements when IFLXgt0 =0 iso-thickness 10 ring elements =1 number of ring elements designated by MESH
1
FACHE When IFLXlt0 amount of He gas given by RODBURN calculation is multiplied by FACHE 10
ICLMAS Coolant unit option =0 flow rate is input in velocity (ms) =1 flow rate is input in mass flow rate (kgcm2s)
0
INPRD
Options for the fetching method of RODBURN results to FEMAXI-7 (Treatment of fast-neutron flux is designated by IFSNT)
INPRD=0 By interpolating the results of RODBURN (the radial and axial
profiles of power fast-neutron flux and He generation) with respect to space and burnup the data are arranged to correspond to the segments in the axial direction of FEMAXI-7
INPRD=1 An identical number of segments in the axial direction is
assumed for FEMAXI-7 and RODBURN The results from RODBURN (the radial and axial profiles of power fast-neutron flux and He generation) are used as data for the corresponding axial segments No spatial interpolation is performed Interpolation of burnup is performed
INPRD=2 The number of segments in the axial direction can be different
for FEMAXI-7 and RODBURN (interpolation processing is performed) With respect to the profiles of power and He generation in the radial direction the result of RODBURN is retrieved For the power profile in the axial direction the input to FEMAXI-7 is used
1
FAIW The fast-neutron flux for a linear power of 1Wcm ((ncm2-sec)(Wcm)) (Fast neutron flux data can be omitted if power history data is input)
5times1011
JAEA-DataCode 2013-009
- 89 -
Name-list Input (2)
Variable name Contents Default value
IPFLX When treating fast-neutron flux as such that is given by input and has a flat profile in the axial direction IPFLX=0 1
IFSNT
Option of fast neutron flux IFSNT=1 FAIW is used the default value of which is 5x1011(ncm2-s) IFSNT=2 Input value is usedWhen the input data is not given LHRtimes
FAIW is adopted IFSNT=3 the value given by RODBURN calculation is used IFSNT=4 a modified value which is given by RODBURN calculation
and is multiplied by FROD is used The default value of FROD is 001
2
FROD When IFSNT=4 fast neutron flux given by RODBURN calculation is multiplied by FROD 001
IRXE When IRXE=1 generated amount of Xe+Kr obtained by RODBURN-1 is used in FEMAXI-7 0
IROD
When IRODgt0 an input file ldquorodinrdquo for RODBURN is generated in the
Wrk directory and FEMAXI-7 calculation is not executed
IROD=1PWR =2BWR =3HaldenBWR =4PWR(MOX)
=5 BWR(MOX)
0
TMCHG Input time for calculation is multiplied by (10+TMCHG) 00 PWCHG Input linear power for calculation is multiplied by (10+TMCHG) 00
SELHST
At line 10 of input list when one of the three quantities A1(time) A2(linear power) and B1(burnup) is to be modified SELHIST is specified SELHIST =0 no modification =1 time is modified
=2linear power is modified =3 burnup is modified
0
STTHST Specifies either the starting time (when SELHIST=1) or burnup (when SELHIST=3) to be modified When SELHIST=2 it is designated either by A1 or B1 in the line No10
00
ENDHST Specifies either the end time (when SELHIST=1) or burnup (when SELHIST=3) to be modified When SELHIST=2 it is designated either by A1 or B1 in the line No10
00
FACHST
Magnification factor for time (when SELHIST=1) linear power (when SELHIST=2) and burnup (when SELHIST=3) In the case that SELHIST=1 and 3 all the input data of times and burnups after ENDHIST are gained by ENDHIST times (FACHST-1)
10
NDIV(1500) Assuming NDIV(I)=N is the input the time-step interval I from historical number I-1 is equally divided by N 15000
ICTP
When CSTMP assigned by line 13 is the cladding surface temperature ICTP=0 is assigned and when CSTEMP is the temperature at the interface of the metallic layer and outer surface oxide film ICTP= 1 is assigned
However even if the oxidation of cladding is not taken into consideration (ICORRO=0) but ICTP=1 a thin oxide film thickness (01microm) is assumed
1
ICSTMP When using degC as the unit for CSTMP which is assigned by the 12-th input line ICSTMP=1 is assigned When the unit is K ICSTMP=0 is assigned 0
JAEA-DataCode 2013-009
- 90 -
Name-list Input (3)
Variable name Contents Default value
IRLHR When IRLHR=0 the axial power profile input in FEMAXI-7 is used When IRLHR=1 the axial power profile obtained by RODBURN is used Effective only when NPRD= either 0 or 1
0
IRFAI
IRFAI is used to assigne the axial segment-wise fast-neutron flux distribution by input
When IRFAI=0 the relative distribution of fast-neutron flux is assumed the same as the relative distribution of linear power
When IRFAI=1 the relative distribution is assigned by the 12-th line of input The relative distribution should be specified by the line 12
When IRFAI= -1 the relative distribution obtained from RODBURN-1 is used
0
ITPLEN When ITPLEN = 1 is assigned the upper- and lower-plenum region temperatures are given by the [ coolant inlet temperature+DTPL] 0
FPLFAC(2) The ratio of fast-neutron fluxes in the upper and lower plenums to those in the adjacent segments of fuel stack (FPLFAC(1) upper-plenum region FPLFAC (2) lower-plenum region)
0505
IFSINP
Interpolation option of fast neutron fluxes at input history points =0 the fast flux at omitted input history points is the same as that at the
previous history point at which flux data is input =1 linear interpolation in terms of burnup is performed for omitted input
points =2 the fast flux dta ashould be input at all the history points They cannot
be omitted
2
ICTINP
Interpolation option of coolant inlet temperature at input history points =0 the temperature at omitted input history points is the same as that at
the previous history point at which temperature data is input =1 linear interpolation in terms of burnup is performed for omitted input
points
1
ICPINP
Interpolation option of coolant pressure at input history points =0 the pressure at omitted input history points is the same as that at the
previous history point at which temperature data is input =1 linear interpolation in terms of burnup is performed for omitted input
points
1
ICVINP
Interpolation option of coolant mass flow rate at input history points =0 the mass flow rate at omitted input history points is the same as that at
the previous history point at which temperature data is input =1 linear interpolation in terms of burnup is performed for omitted input
points
1
IRH
Interpolation option of axial power profile at input history points =0 the profile at omitted input history points is the same as that at the
previous history point at which temperature data is input =1 linear interpolation in terms of burnup is performed for omitted input
points
0
IBUOP
Option of time vsburnup at input history points IBUOP= -1 time is calculated with the input sets of burnup and linear power IBUOP=0 time is calculated with the input sets of burnup and average linear power IBUOP= n time is calculated with the input sets of burnup and linear power at n-th axial segment
-1
JAEA-DataCode 2013-009
- 91 -
Name-list Input (4) Variable name Contents Defauly
value
Calculation options
IFEMOP
= -1 only thermal analysis is executed (non-coupled calculation of thermal analysis and mechanical analysis)
= 0 coupled calculation of thermal analysis and mechanical analysis
IFEMRD designates the option of mechanical analysis
= 2 coupled calculation of thermal analysis and mechanical analysis IFEMRD designates the option of mechanical analysis
2
IFEMRD =0 2-D local mechanical analysis (Mechanical analysis II) =1 Entire rod length (ERL) mechanical analysis (Mechanical analysis I) 1
ZR
Thickness of Zr liner inside the cladding (cm) If cladding has no liner ZR=00 Restart calculation automatically takes over the value specified in
[Base-calculation]
00
IREST
In FEMAXI-7 calculation (1) =0 Analysis only by FEMAXI-7 =1 only 1-D calculation for FURBEL =2 generating Restart file (ft11) fro RANNS In this case the cladding has the same ring elements division as that of
RANNS
0 In FEMAXI-7 calculation (2) =4 generating Restart file (ft11) for FEMAXI and RANNS
allowing the designation of segments for refabricated short rod In FEMAXI-7 Re-start calculation (3) =5 reading the restart file (ft11) of FEMAXI-7 by FEMAXI-7 to
perform the calculation of test-irradiation for the axial segments designated by TRSGT However the objective segment for 2-D mechanical analysis in the base-irradiation calculation should be the same as the axial segment designated by TRSGT
JAEA-DataCode 2013-009
- 92 -
Name-list Input (5)
Variable name Contents Default value
TRSGT(2)
This is designated in the case where IREST=5 in FEMAXI If this condition is not met error message is issued and calculation will not start Ex suppose a rod has 10 axial segments in base-irradiation calculation and re-start calculation is performed for 4- 5- and 6-th segments ldquoTRSGT=4 6rdquo If only 5-th segment is dealt with ldquoTRSGT=5rdquo When IFEMRD=0 the objective segment (IFEM) in the base-irradiation calculation has to be cincluded in the designation by TRSGT For example in the case where IFEM=5 in base-irradiation and TRSGT=46 IFEM in restart calculation has to be IFEM=2 Otherwise error message is issued and no calculation will start
0 0
IRTIME
When IRTIME=0 in the input file of Re-start calculation time (or burnup) has to be input as a sequential value from the beginning of base-irradiation
However if time is input burnup at EOL of base-irradiation calculation is taken over to be an initial burnup of Re-start calculation
When IRTIME=1 time at the start of Restart calculation has to be 0 and
with this initial time=0 the Re-start irradiation history has to be given in input file However in Re-start calculation burnup at EOL of base-irradiation calculation is taken over and added to the initial burnup of Re-start input file
1
NAXSG
Option to select the method of axial force calculation in ERL mechanical analysis
NAXSG=0 in each axial segment axial force is transmitted to its lower adjacent segment Reaction force to the axial force at the segment-segment interface is not taken into consideration
NAXSG=2 each segment displaces independently In each segment axial
force is determined by PCMI within the segment irrespective of the PCMI conditions in the other segments
0
JAEA-DataCode 2013-009
- 93 -
Name-list Input (6)
Variable name Contents Default value
MESH
Number of ring elements of pellet stack 1-D thermal 1-D mechanical 2-Dlocal mechanical
MESH=0 iso-thickness10 iso-thickness 10 iso-thickness 5 MESH=1 iso-volume 36 iso-volume 18 iso-volume 9 MESH=2 iso-volume 72 iso-volume 18 iso-volume 9 MESH=3 iso-volume 36 iso-volume 36 iso-volume 18 MESH=4 iso-volume 72 iso-volume 36 iso-volume 18
However when HBS option (high burnup structure model) is designated MESHgt0 has to be set
When ISHAPE=1 is selected the above number of ring elements is doubled ( In RANNS when IRESTgt0 ldquoMESHrdquo value is automatically taken over from FEMAXI-7 ) Here number of cladding ring elements is irrespective of
ldquoMESHrdquo designation as follows For 1-D thermal and mechanical models 1) Cladding which has no Zr-liner
8 metallic elements + 2 outer oxide layers 2) Cladding with Zr-liner
2 liner elements + 8 metallic elements + 2 outer oxide layers For 2-D local mechanical model 3) Cladding which has no Zr-liner
4 metallic elements + 1 outer oxide layers 4) Cladding with Zr-liner
1 liner elements + 4 metallic elements + 1 outer oxide layers However when ISHAPE=1 the above number of elements is doubled Restart calculation automatically takes over the value specified in [Base-calculation]
3
ARC(4) When IFEMRD=0 ie in 2-D local mechanical analysis the ratio of four element widths in the radial direction can be given by ARC 410
AXBND When IFEMRD=0 ie in 2-D local mechanical analysis AXBEND=1 gives a boundary condition which allows the free displacement of each node in pellet upper end plane in the axial direction
0
INPCK Input data check option (=0 normal calculation =1 input check only) 0
ICHI
Elasticity calculation option when IFEMRD=0 = 0 normal calculation = 1 elasticity calculation only Neither creep nor plasticity is taken into
consideration
0
K1
Number of elements in the axial direction per half a pellet length in the local mechanical analysis (K1 le 5) When ISHAPE=1 this number is doubled ie K1times2 Restart calculation automatically takes over the value specified in [Base-calculation]
3
JAEA-DataCode 2013-009
- 94 -
Name-list Input (7)
Variable name Contents Default value
AZ1(5)
When IFEMRD=0 the ratio of element sizes in the axial direction can be given by AZ1 for the K1 elements per half a pellet length When ISHAPE=1 AZ1 is applied to each 2-element set That is AZ1(I) is applied to (2I-1)th and (2I )th elements Restart calculation automatically takes over the value specified in [Base-calculation]
510
IRM Option for the cladding material (=0 Zircaloy =1 Stainless) 0
ILOCK When IFEMRD=0 axial force treatment option ILOCK=0 locking model =2 no axial force is taken into account 0
IFIX When IFEMRD=0 if contact between pellet and cladding is always assumed as ldquobonding staterdquo designate IFIX=1 0
TLIM Truncation control of CPU time (When the execution time reaches TLIM (s) calculation is terminated by the code itself) 200000
IZERO
Option to calculate and output the quantities such as internal pressure inner space volume cladding size etc at zero-power state in the calculation along the input history data
=0 No calculation at zero-power =1 zero-power calculation is performed with zero-power state temperature
being assumed as TROOM =2 zero-power calculation is performed with zero-power state temperature
being assumed as that at start-up =3 zero-power calculation is performed with zero-power state temperature
being assumed as that of the coolant temperature at that time =4 zero-power calculation is performed with input designated temperature
TZERO
0
TZERO Zero-power state temperature used when IZERO=4 (K) 29115
IELAST
Option of elastic calculation in ERL mechanical analysis =0 regular analysis =1 plasticity and creep of the pellet and cladding are ignored =2 plasticity and creep of the pellet are ignored =3 plasticity and creep of the cladding are ignored
0
IS3P
Option to control the thermal-hydraulics calculation when using the input-specified condition for cladding surface temperature IS3P=0 no thermal-hydraulics calculation is performed
IS3P=1 thermal-hydraulics calculation is performed IS3P=2 when IHF=1 in order that calculation can be continued even if Na-coolant temperature becomes lower than 200oC at a certain history point mode change has to be done into IS=3 or =4 in which cladding surface temperature can be specified by input At the same time thermal calculation of Na-coolant is stopped at this history point
However even when IS3P=0 to perform mechanical calculation of creep down of cladding induced by external coolant pressure the coolant pressure values are maintained at the input values
0
ILNR When IFENRD=0 for stress calculation ILNR=1 Newton-Raphson method is applied ILNR=0 Newton-Raphson method is not applied
0
SIGNR When IFEMRD=0 SIGNR is a permissible error (MPa) for the stress calculated by Newton-Raphson method 01
JAEA-DataCode 2013-009
- 95 -
Name-list Input (8)
Variable name Contents Default value
Options for mechanical properties of cladding oxide and liner and options for hollow pellet
MATXO
=0 mechanical properties of ZrO2 are applied to those of the cladding outer oxide layer
=1 mechanical properties of cladding outer oxide kayer are replaced with those of Zircaloy by designating the values in FACXO
0
FACXO(5)
Option to multiply the mechanical properties values of cladding outer oxide layer by FACXO Effective when MATXO=1 (FACXO(1) Youngrsquos modulus FACXO(2) Poissonrsquos ratio FACXO(3) thermal expansion rate FACXO(4) creep rate FACXO(5) yield stress)
510
MATLNR
(Effective when ZRgt0) Option for mechanical propereties of Zr liner of cladding =0 mechanical properties of pure Zr are applied to the Zr liner =1 mechanical properties of liner are replaced with those of Zircaloy by
designating FACLNR
0
FACLNR(5)
(Effective when ZRgt0 and MATLNR=1) Option to multiply the mechanical properties values of cladding liner by FACLNR (FACLNR(1) Youngrsquos modulus FACLNR(2) Poissonrsquos ratio FACLNR(3) thermal expansion rate FACLNR(4) creep rate FACLNR(5)yield stress)
510
PDPRF
When both solid pellets and hollow pellets exist in one fuel rod power density profile in the radial direction of pellet is adjusted by taking account of the centerhole void
When PDPRF=0 the hollow pellet segment uses the profile in which the center part is eliminated from the solid pellet relative profile (average=10) Numerical output or plotted figure show the LHR which is calculated by this profile so that the LHR value is to a small extent lower due to the null power in the centerhole region
When PDPRF=1 the hollow pellet segment uses the power profile which is obtained by multiplying the profile of ldquoPDPRF=0rdquo with factor f(gt10) to hold the LHR unchanged as if the segment pellet were solid even in the presence of centerhole This factor is constant in the radial direction
0
MXHIST Maximun number of input history points 1500 LD Size of DIMENSION of real number array 4000000
LID Size of DIMENSIONof integer array 500000 【Note 1】The message ldquoDIMENSION AREA OVER FLOW LTSM =xxxxx LD =4000000rdquo is output and the program execution is terminated when LTSMgtLD To avoid this it is necessary to designate LD by name-list input to make LDgtLTSM At the same time ldquo4000000rdquo in the statement ldquoDIMENSION
ID(500000) D(4000000)rdquo in ldquomainforrdquo has to be changed into the value which is specified by LD and compilation of the source program has to be performed again 【Note 2】The message ldquoDIMENSION AREA OVER FLOW LASI=xxxxx LID =500000rdquo is output and the program execution is terminated when LASIgtLID To avoid this it is necessary to designate LID by name-list input to make LIDgtLASI At the same time ldquo5000000rdquo in the statement ldquoDIMENSION
ID(500000) D(4000000)rdquo in ldquomainforrdquo has to be changed into the value which is specified by LID and compilation of the source program has to be performed again
JAEA-DataCode 2013-009
- 96 -
Name-list Input (9) Variable name Contents Default
value
ITBFIX Option to make fuel temperature equal to coolant temperature at 0 power state Effective when ITBFIX=1 1
ISHAPE
Option for type of finite element in 2-D local mechanical analysis ISHAPE=1 Rectangular four-node element with linear shape function ISHAPE=2 Rectangular eight-node element with quadratic shape function Restart calculation automatically takes over the value specified in
[Base-calculation]
2
CHKVAL(10)
Upper limit of checking abnormal values CHKVAL(1) cladding equivalent stress (MPa) CHKVAL(2) pellet center temperature (oC) CHKVAL(3)cladding temperature (oC)
10000 30000 30000
70
ICHK(10) Option to continue calculation even if abnormal value is detected ICHK=0 calculation is continued ICHK ne 0 calculation is stopped
101
ICKOPT
Option to specify the time-step interval using check function argument for checking abnormal values =0 checking calculation only at the input history points
=1 checking calculation at all the time-steps = -n (when n 1 or n 10ne ne ) checking calculation at every n steps = -1 checking calculation at the time-steps exceeding DT_OUT except
the input history points DT_OUT is an option for putput = -10 checking calculation at all the time-steps from PLTIME(1) to
PLTIME(2) However input history points are always included in checking points PLTIME is an option for output
0
DDSIGE Maximum allowable change of equivalent stress in the iteration calculation of ERL (IFEMRD=1) mechanical analysis (MPa) 10
DDSIGE2 Maximum allowable change of equivalent stress in the iteration calculation of 2-D (IFEMRD=0) mechanical analysis (MPa) 100
DLSIGE Allowable error of the maximum change of equivalent stress in the iteration calculation of ERL (IFEMRD=1) mechanical analysis (MPa) 1000
DLSIGE2 Allowable error of the maximum change of equivalent stress in the iteration calculation of 2-D (IFEMRD=0) mechanical analysis (MPa) 2000
ISIGE
Option to continue calculation even if allowable error of the maximum change of equivalent stress is detected in the iteration calculation of ERL (IFEMRD=1) mechanical analysis ISIGE= -1 calculation continues without output of iteration process ISIGE= 0 calculation continues with a simplified output ISIGE= 2 calculation continues with detailed output ISIGE=1 calculation stops with detailed output
1
ISIGE2
Option to continue calculation even if allowable error of the maximum change of equivalent stress is detected in the iteration calculation of 2-D (IFEMRD=0) mechanical analysis ISIGE2= -1 calculation continues without output of iteration process ISIGE2= 0 calculation continues with a simplified output ISIGE2= 2 calculation continues with detailed output ISIGE2=1 calculation stops with detailed output
1
AJUDG1 Temperature error limit in the convergence calculation of temperature dependence of thermal conductivity (oC) 01
ICONVX Maximum number of times of the convergence calculation of temperature dependence of thermal conductivity 20
JAEA-DataCode 2013-009
- 97 -
Name-list Input (10) Variable name Contents Default
value
Calculation conditions
AJUDG2 Temperature error limit in the convergence calculation of gap thermal conductance (oC) 10
ICONV2 Maximum number of times of the convergence calculation of gap thermal conductance 100
AY Tilting of the pellet upper surface in the case of dished pellet AY=0 (cm) Effective only when IFEMRD=0 In a dished pellet AY=00 0002
TROOM Room temperature or fuel rod initial temperature (K) 29115
ITIME(20) An option for changing plenum gas pressure and gas composition A historical point number for changing is inputted to ITIME(I) (up to a
maximum of 20 ) 200
GASPRN(20) The plenum gas pressure (MPa) at a historical point number ITIME(I) is assigned by GASPRN(I) 2000
PLENM(20) The plenum volume (cm3) at a historical point number ITIME(I) is
assigned by PLENM(I) (Note this is not the volume of the fuel free space but the volume at the plenum part)
2000
GMIXN(4 20) Gas composition at history point number ITIME (minus) Molar ratios of gas
compositions at ITIME(I) are specified by GMIXN(1 I) to GMIXN(4 I) where 1 =He 2 = N2 3 =Kr 4 =Xe
8000
DEN(20) Equivalent diameter (cm) of coolant flow area at history point ITIME(I) is designated by DEN(I) At least more than one of DEN FAREAN and PITCHN have to be designated
2000
FAREAN(20) Cross sectional area of coolant channel (cm2) at ITIME(I) is designated by FAREAN(I) At least more than one of DEN FAREAN and PITCHN have to be designated
2000
PITCHN(20) Rod-to-rod pitch (cm) at ITIME(I) is designated by PITCHN(I) At least more than one of DEN FAREAN and PITCHN have to be designated 2000
GAPLK Minimum gap width at which axial force by PCMI is generated (microm) 30 XKSU Upper plenum spring constant (Nm) 15000 ALSU Upper plenum spring thermal expansion coefficient (1K) 15times10-5 XKSL Lower plenum spring constant (Nm) 25000 ALSL Lower plenum spring thermal expansion coefficient (1K) 15times10-5 AMU Friction coefficient between pellet and cladding (IFEMRD=0) 04 AMU2 Friction coefficient between pellet and cladding (IFEMRD=1) 04 DE Equivalent diameter of coolant channel (cm) 00 FAREA Cross sectional area of coolant channel (cm2) 00 PITCH Pitch between fuel rods (cm) (CDOUT cladding outer diameter (cm)) CDOUTtimes13
NRCZR Number of radial elements the metal wall of cladding in the entire rod length mechanical analysis 8
NRCOX Number of radial elements in the outer oxide layer of cladding in the entire rod length mechanical analysis 2
DTPL Temperature difference between gas inside the plenum and surrounding coolant (K) Plenum temperature = Coolant temperature + DTPL (K) 250
LBU
When LBU=1 is set calculation uses the local burnup in the radial direction of pellet and when LBU=1 calculation uses the average burnup
Restart calculation automatically takes over the value specified in [Base-calculation]
1
JAEA-DataCode 2013-009
- 98 -
Name-list Input (11) Variable name Contents Default
value
XLSZU
The axial length of the upper plenum part used in the entire length mechanical analysis (cm) When XLSZU is not assigned (XLSZU=00) it is given by the value obtained by dividing the upper-plenum volume PLENUM (2) which is
assigned by line 8 by 2cirπ ( cir = inner radius of cladding)
00
XLSZL
The axial length of the upper plenum part used in the entire length mechanical analysis (cm) When XLSZL is not assigned (XLSZL=00) it is given by the value obtained by dividing the upper-plenum volume PLENUM(1) which is assigned by line 8 by 2
cirπ ( cir = inner radius of cladding) When PLENUM (1)=00 no lower plenum is assumed to
exist even if XLSZL is designated
00
IRELCV
Option to take into account of the space volume (spaces of crack dish and chamfer) change inside pellet during irradiation IRELCV=0 not taken into account IRELCV=1 taken into account The code calculates the relocation strain relε in the radial circumferential
and axial directions This strain relε changes by the internal compressive stress inside pellet induced by power change
0
IQREAT Option for the reaction heat generated by oxidation of cladding IQREAT=0 not taken into account IQREAT =1taken into account 0
GAMHT When GAMHT=1 γ-heating is added to the thermal calculation of cladding 0
GAMHG γ-heating rate of cladding (Jg) effective when GAMHT=1 10
GAMRC Proportion factor of γ-heating rate of cladding to the metal density and pulse power effective when GAMHT=1 10
IHF When IHF=1 coolant is assumed to be Na 0
NUOP
Option for Nu number to be used in the equation of thermal conductance from claddint to Na coolant
When NUOP=1 80Pr)(Re030036 +=Nu
When NUOP=2 0870 0025PeNu = + Here Pe max(Re Pr 200)=
1
SUBCL When SUBCL=1 if the input-specified inlet coolant temperature exceeds the saturation temperature coolant density at the inlet is made equal to the density of liquid phase coolant at saturation temperature
1
JAEA-DataCode 2013-009
- 99 -
Name-list Input (12) Variable name Contents Default
value
Time step control DPXX Power increment width per unit time step (Wcm) 100 DPBU Burnup increment width per unit time step (MWdtUO2) 1000
IPH IPH=0 when the control of DPXX and DPBU is set to be the objective segment (IFEM) and IPH=1 when it is set to be the peak power segment 1
EFCOEF
Time step width determination factor due to creep
∆tE c
=sdot
sdotσ
εEFCOEF
where σ is equivalent stress E is Youngrsquos modulus and ε c is equivalent creep strain rate
01
MAXTM
Maximun number of time-step controls in one time-step in the ERL mechanical analysis This controls follow P-C contact state changes between contact and non-contact state and changes between plastic and elastic state changes
42
LCMAX Maximum number of judgments of clogged or sliding state of the contact between pellet and cladding when IFEMRD=1 10
LMAX Number of iterations in the Newton-Raphson method for deformation Calculationwhen IFEMRD=1 (LMAX le 100) 20
ITEND
Number of repetitions of Newton-Raohson method in the deformation calculation of 2-D local mechanical analysis ( IFENRD=0) where the first calculation is not included in the repetition so that ldquoITEND=Nrdquo means (N+1) times repetitions
1
ITIMY
Time step control option for elasticityplasticity judgment when IFEMRD=0 and 1
= -1 without time step control = 0 time step control is performed only upon the removal of load = 1 with time step control)
-1
JAEA-DataCode 2013-009
- 100 -
Name-list Input (13) Variable name Contents Default
value Options for pellet thermal conductivity
IPTHCN
Options for fuel pellet thermao conductivity models =1 MATPRO-09 =2 Washington =3 Hirai =4 Halden =5 Modified Hirai =6 Forsberg =7 Kjaer-Pedersen =8 BaronampCouty =9 OhiraampItagaki =10 Lucta MatzkeampHastings =11 Tverberg Amano Wiesenack (Gd-containing fuel) =12 Sontheimer Landskron Billaux (Gd-containing fuel) =13Fukushima (Gd-containing fuel) =14HiraiIshimoto (Gd-containing fuel) =15Daniel Baron (UO2 Gd-containing fuel ) =16 KitajimaampKinoshita =17 Wiesenack(Halden_New) =18 PNNL modified Halden model =90 Ohira amp Itgaki original =91 Ohira amp Itgaki latest model for UO2 and MOX =92 Modified ldquoOhira amp Itagaki modelrdquo in FRAPCON 33 =30Martin(MOX) =31MATPRO-11(MOX) =32Martin+Philipponneau(MOX) =33Duriez et al(MOX) =34Philipponneau(MOX) =35 Halden (new MOX) =36Daniel Baron (MOX Gd-containing fuel) =37 PNNL-modified Halden model in FRAPCON-2-3 =38 PNNL model in FRAPCON-3 based on the Duriez model
17
IZOX Option for thermal conductivity of cladding oxide layer model =1MATPRO-A(Zircaloy) =2MATPRO-11(Zircaloy) =41SUS304
2
ITMC Option for cladding thermal conductivity model =1MATPRO-09 (Zircaloy) =40SUS316 =41SUS304
1
Options for MOX fuel and parameters for pellet thermal conductivity
PU(40)
PuO2 weight fraction at each axial segment (-) It is assumed that segments of PU(I)gt0 have MOX fuel and segments of PU(I)=0 have UO2 fuel
Totally NAX number of PU(I) are designated
( )2
2 2
PuOPu= weight ratioUO +PuO
Restart calculation automatically takes over the value specified in [Base-calculation]
4000
PUFIS(40)
Fissile Pu concentration at each axial segment (-) PUFIS is weight fraction of fissile Pu to total weight of Pu Totally NAX
number of PUFIS(I) are designated Restart calculation automatically takes over the value specified in
[Base-calculation]
4000
JAEA-DataCode 2013-009
- 101 -
Name-list Input (14) Variable name Contents Default
value Y Value of y in MO2-y used when IPTHCN=15 and 36 00 LT Lattice spacing parameter used when IPTHCN=15 and 36 (Aring) 54702
GD Gd2O3 concentration (weight fraction) Restart calculation automatically takes over the value specified in
[Base-calculation] 00
FPTH Magnification factor for pellet thermal conductivity 10
CBU Burnup(MWdkg-UO2)-dependent parameter used when IPTHCN=11
00046 (UO2 fuel) 00056 (Gd-containing fuel)
CGD Gadolinia conc(wt)-dependent parameter used when IPTHCN=11 00066
SLB(6)
SLB(1)=a SLB(2)=b SLB(3)=Dbu SLB(4)=Dgd SLB(5)=Cbu SLB(6)=Cgd
Used when IPTHCN=12 See pellet thermal conductivity model described
in Chapter 4
00235 255times10-4
00949 042
10times10-4
956times10-4
M1
As one of the thermal conductivity models of MOX fuel the model of
IPTHCN=35 multiplies a factor KMOX on the thermal conductivity of UO2
fuel KMOX is assumed by the equation
1 12
(1 ) 1 exp BuM MBu
= minus minus minus +
KMOX and M1 is the value of M1
092
BUMOX KMOX is assumed by the equation
1 12
(1 ) 1 exp BuM MBu
= minus minus minus +
KMOX and BUMOX is the value of Bu2 400
KMOX
When the equation 1 12
(1 ) 1 exp BuM MBu
= minus minus minus +
KMOX is applied to
the other models of UO2 thermal conductivity (IPTHCN=1 -18) ie to use
the UO2 thermal conductivity models which are multiplied by KMOX as
MOX fuel thermal conductivity KMOX=1 is designated
0
JAEA-DataCode 2013-009
- 102 -
Name-list Input (15) Variable name Contents Default
value
IPRO
Option to specify the effect of pellet porosity p=10-D(I)Di (or theoretical density ratio D(I)) on the pellet thermal conductivity where Di is the initial density Refer to Eqs(2327) and (2328) =0 Initial porosity 0p assuming D(I)=Di is used
=1 Porosity defined by 0
0
swgVp p
V∆
= + is used
=2 Porosity defined by 00 0
dens hotV Vp pV V
∆ ∆= + + is used
=3 Porosity defined by 00 0 0
swg dens hotV V Vp pV V V
∆ ∆ ∆= + + + is used
where Di the initial theoretical density ratio 0p initial porosity
0
swgVV
∆ fission gas bubble swelling irrespective of IFSWEL
0
densVV
∆ densification calculated by the model designated by IDENSF
and 0
hotVV
∆ volumetric strain by hot-press
However this porosity calculation is not performed ring element-wise
It is performed at each axial segment and average porosity over one
segment is obtained Plot output is by IDNO=57 and pellet density =1-p
0
MPORO
Option for the effect of porosity on the thermal conductivity of pellet
=0 pellet thermal condcutivity at each axial segment is calculated by using the porosity which is designated by IPRO
=1 pellet thermal condcutivity at each axial segment is calculated by
using the ring-element-wise porosity 00 0
swg densV Vp pV V
∆ ∆= + +
Here definitions of swelling and densification are identical to those by IPRO However ring-element-wise change of porosity obtained by HBS model is independent from MPROR designation The effect of porosity by HBS model at eack ring element can be taken into account in calculation irrespective of MPORO designation
Corresponding plotter output is IDNO=257 total porosity IDNO=260 fission gas bubble porosity
0
JAEA-DataCode 2013-009
- 103 -
Name-list Input (16) Variable name Contents Default
value Options for density
IPDENS
In the mechanical analysis all factors concerning the pellet density ie 1D p= minus and 01Di p= minus are taken into account This option is to select
the factors to be output by plotter The porosity of pellet is obtained by one of the following equations
IPDENS=1 00 0
swg densV Vp pV V
∆ ∆= + +
=2 00 0 0
swg dens hotV V Vp pV V V
∆ ∆ ∆= + + +
=3 00 0 0 0
swg dens hot relV V V Vp pV V V V
∆ ∆ ∆ ∆= + + + +
=4 00 0 0 0 0
swg dens hot rel thV V V V Vp pV V V V V
∆ ∆ ∆ ∆ ∆= + + + + +
where Diinitial theoretical density ratio 0p initial porosity (1- Di)
0
swgVV
∆swelling calculated by the model designated by IFSWEL
0
densVV
∆ densification calculated by the model designated by IDENSF
0
hotVV
∆ hot-pressing
0
relVV
∆relocation-induced change and
0
thVV
∆ volumetric change by thermal expansion
The corresponding plotter outputs are
IDNO=79 segment average porosity designated by IPDENS
IDNO=80 segment average volumetric change designated by IPDENS
IDNO=281 pellet density change (D=1 - p) of each ring element of
segment designated by IPDENS=1
=282 pellet density change (D=1 - p) of each ring element of
segment designated by IPDENS=2
=283 pellet density change of each ring element of segment
designated by IPDENS=3
=284 pellet density change of each ring element of segment
designated by IPDENS=4
1
ICDENS Option for cladding density =1 Zircaloy =41 SUS304 1
JAEA-DataCode 2013-009
- 104 -
Name-list Input (17) Variable name Contents Default
value Options for specific heat
ISPH Option for equation of pellet specific heat =1 MATPRO-11 =30 MATPRO-11 =31 SGTE Database 1
ICSPH Option for equation of cladding specific heat =1 MATPRO-09 (Zircaloy) =41 MATPRO-A (SUS-304) 1
Options for gap thermal conductance
IGAPCN
Option of gap thermal conductance (IGAPCN=5 and 6 are thermally bonding models) =0 Modified Loss amp Stoute =1 MATPRO-09 =2 Loss amp Stoute =3 modified Dean =4 Modified Loss amp Stoute (new) =5 Bonding model 1 (combination of UO2+ZrO2+Open Gapcon) =6 Bonding model 2 (combination of UO2+ZrO2 only even if the gap is
re-opened) =7 gap conductance is fixed at the value specified by GAPCN
0
R1 (Used when IGAPCN = 0 or 2) pellet surface roughness (microm) 10 R2 (Used when IGAPCN = 0 or 2) cladding surface roughness (microm) 10
IAR
Option to change the second element of gas from the standard lsquoN2rsquo When using Ar in place of N2 IAR=rsquoARrsquo When IAR=rsquoARrsquo gas properties
such as GG2 AA2 BB2 and WW2 are automatically set When changing to the gas other than Ar the properties are required to be specified by input
lsquoN2rsquo
GG2 Jump distance between solid and gas (cm) which is used when IAR designates the gas other than N2 Default value is for Ar 50times10-4
AA2 Coefficient a in the equation K=aTb (Wm K) of gas thermal conductivity which is used when IAR designates the gas other than N2 Default value is for Ar
3421 times10-6
AB2 Coefficient b in the equation K=aTb (Wm K) of gas thermal conductivity which is used when IAR designates the gas other than N2 Default value is for Ar
0701
WW2 Molar mass of gas which is used when IAR designates the gas other than N2 Default value is for Ar 39948
OXEMS Oxide emissivity =1Zircaloy =41SUS304 =41SUS316 1
IXEKR XeKr ratio option =0XeKr=8713 =1 XeKr=8614 =2XeKr=16 =3 data from PLUTON is used ( effective only when IFLX= -1)
0
FACPC (Used when IGAPCN = 0 or ge 4) Solid-solid contact term of gap thermal conductance is multiplied by FACPC 10
PC0 (Used when IGAPCN = 4) Reference contact pressure when PCMI occurs 30 X When IGAPCN=4 an exponent for the contact pressure function 30 FACS (IGAPCN = 4) Multiplying factor for solid thermal conductance term 100
TGPG
Option for gap gas temperature TGPG=0 gap gas temperature is set to the average of temperatures at pellet outer surface and cladding inner surface TGPG=N (gt0) gap gas temperature is set to the average of temperatures at the N-th ring element of pellet
0
FGCN Multiplying factor to assume thermally isolated state of P-C gap 10 GAPCN Fixed gap thermal conductance used when IGAPCN=7 (Wcm2K) 05678
JAEA-DataCode 2013-009
- 105 -
Name-list Input (18) Variable name Contents Default
value Options for cladding surface heat transfer model
AKFAC Multiplying factor for the surface heat transfer coefficient of cladding 10
ISCNHAL When ISCNHAL=1 Halden empirical equation is used for the surface heat transfer of cladding Effective when IS=0 1 and 2 0
CSTEM Cladding surface temperature is fixed at the value specified by CSTEM if CSTEM(K) is input Effective when ISCNHAL=0 and IS=0 1 and 2 00
ITSAT
When ITSAT=0 and coolant inlet temperature is higher than [saturation temperature ndash 01] the coolant inlet temperature is set equal to [saturation temperature ndash 01] When ITSAT=1 the inlet temperature is used as is input and inflow of overheated steam is allowed in calculation
0
JL
Option for the surface heat transfer equations in nucleate boiling regime =0 Chenrsquos equation (mailnly for PWR) =1 Jens-Lottes equation (mainly for BWR)
Jens-Lottes equation is applicable to the nucleate boiling region which has a low void ratio (cross section of steamtotal flow cross section) and is used in mailny sub-cooled boiling of water Chenrsquos equation is an evaluation formula which is arranged on the basis of the overheating degree ΔTsat of conduting surface
1
ICFL
When ICFL=1 when the coolant temperature exceeds the cladding temperature in the calculation the cladding temperature is set equal to the coolant temperature and the material properties such as the enthalpy of coolant quality and void fraction are reset using the cladding temperature Option for transient calculation
0
DCNL
Diameter of channel inner tube (cm) When a fuel rod is irradiated inside an inner tube contained in a capsule heat flux loss ocurrs from coolant inside the inner tube to the outer space of the inner tube To approximate this situation the heat flux is calculated by specifying the inner diameter of inner tube coolant temperature at the inlet to the outer space of the inner tube and thermal conductance across the inner tube wall This mode is ON when DCNLgt0
00
TCEXT(20) Coolant inlet temperature (K) at the space outside the inner tube This is different from TCOOL 3000
ICINT(2) In the period between ICINT(1) and ICINT(2) heat outflux through the inner tube channel is taken into account Input the designated history point number to ICINT(1) and ICINT(2)
20
HX(20)
Surface heat conductance (Wcm2K) at the outer surface of the inner tube channel in the period specified by ICINT For example when ICINT(1)=5 and ICINT(2)=10 this period consists of 6 intervals from history point number 6 to 10 However as HX is interpolated with time during the period totally 7 values of HX are specified in HX(1) to HX(7) which is spanned from the beginning of history point 5 to the end of history point 10
2000
FACQJS Fraction of contribution by cladding outer surface heat flux to coolant enthalpy increase 10
JAEA-DataCode 2013-009
- 106 -
Name-list Input (19) Variable name Contents Default
value
Options for FGR model -1-
IGASP
Option for fission gas release model IGASP=0 equilibrium model of grain boundary gas bubbles +intra-grain
bubble model IGASP=2 rate-law model of grain boundary gas bubbles +intra-grain
bubble model Restart calculation automatically takes over the value specified in
[Base-calculation]
0
GBFIS
Option for intra-granular gas bubble model ie model for bubble radius and number density GBFIS=0 White+Tucker model GBFIS=1 Irradiation-induced dissolution model GBFIS=2 Pekka Loumlsoumlnen model
0
APORE (Effective when IGASP=0 or 2 and GBFIS=0) Initial radius of intra-granular gas bubble (nm) 10
KFIS (Effective when IGASP=0 or 2 and GBFIS=0) Exponent used in the equation to determine destruction rate of intra-granular bubbles 20
RFIS (Effective when IGASP=0 or 2 and GBFIS=1) Reference bubble radius (nm) used to determine destruction rate of intra-granular bubbles Initial radius of intra-granular gas bubble (nm)
200
GSV (Effective when IGASP=0 or 2 and GBFIS=1) Tuning factor of surface energy equation of UO2 041
KV (Effective when IGASP=0 2 and GBFIS=1) Tuning factor of vacancy diffusion coefficient 10
RADMG (Effective when GBFIS=2) Upper limit radius of intra-granular gas bubble (nm) 1000
GROU (Effective when GBFIS=2) Initial density of intra-granular gas bubble
0ρ (gcm3) 40
BBC (Effective when GBFIS=2) Parameter to adjust re-dissolution rate (cm3) 3times10-17
RROU (Effective when GBFIS=2) Threshold radius of intragrain bubble Rρ (nm)
under which the initial bubble density 0ρ is kept unchanged 100
NROU
(Effective when GBFIS=2) Value of Nρ in the equation below defining
the bubble density when intra bubble radius exceeds Rρ (RROU)
Namely when R Rρge 0
NiniRR
ρ
ρ ρ
=
10
IRIM
(Effective when IGASP=0 and 2 and only when HBS=0) Model option for (additional) fission gas release from rim region
=0 additional FGR from rim is not taken into account =1 Battelle model =2 Cunningham model
=3 Cunningham model applied to the outermost ring element only =4 Lassmann empirical model
Restart calculation automatically takes over the value specified in [Base-calculation]
1
JAEA-DataCode 2013-009
- 107 -
Name-list Input (20) Variable name Contents Default
value
Options for FGR model -2- BFCT Re-dissolution rate of in-grain bubbles into matrix is multiplied by BFCT 10
FFL Lower boundary value of fission rate F (fissionscm3s) in calculating the re-dissolution rate bprime of fission gas atoms from intra-grain bubbles to solid matrix
1013
IDCNST Option for models of fission gas atom diffusion constant equation =1 Turnbull et al =2 White amp Tucker =3 Kitajima amp Kinoshita =4 Modified Turnbull =5 White =6Kogai
1
IFIS Option for fixing the fission rate which is used in calculating fission gas
atom diffusion coefficient =0 fission rate is not fixed =1 fixed at 1019fissionsm3s
1
FACD Effective diffusion coefficient in grain is multiplied by FACD 10 DIFM Upper limit of fission gas atoms diffusion coefficient(cm2s) 10-8
AM1 When IDCNST=4 an adjusting factor of temperature dependent term of fission gas atoms diffusion coefficient 10
BM1 When IDCNST=4 an adjusting factor of temperature non-dependent term of fission gas atoms diffusion coefficient 10
FGDIFX Option to adjust the temperature dependence of fission gas atoms diffusion coefficient To adjust ie to mulpiply the term FGDIFX=1 is designated If not FGDIFX=0is designated
0
FGDIF0 Factor to multiply the term to adjust the temperature dependence of fission gas atoms diffusion coefficient 100
EFA Parameter a to adjust the temperature dependence of FGDIF0 60
ADDF Re-dissolution rate of gas atoms in grain boundary bubbles into grain matrix is multiplied by ADDF 90
FBSAT Amount of gas saturation at grain boundary is multiplied by FPSAT (Effective when IFSWEL=0 234 and 5) 10
PSAT Limiting pressure acting on grain boundary bubbles (Pa) (Effective when IPEXT=0 12 and 3) 108
RF
Upper limit of inter-grain gas bubble radius At this radius gas is released and bubble will not grow (cm) Restart calculation automatically takes over the value specified in
[Base-calculation]
50times10-5
FBCOV Fraction of coverage of inter-grain gas bubble on grain boundary surface
Restart calculation automatically takes over the value specified in [Base-calculation]
025
ALHOT (Used when IPEXT=1112 and 13) Hot press parameter for the average stress acting on the grain boundary bubbles
10-4
APEXT (Used when IPEXT=14) Pext average stress obtained in the entire rod length mechanical analysis is multiplied by APEXT 10
ISFTN Option for surface energy of pore in UO2 crystal ISFTN=0626 (ergcm2) ISFTN=1Hall and Mortimer model 0
JAEA-DataCode 2013-009
- 108 -
Name-list Input (21) Variable name Contents Default
value
Options for FGR model -3- OPORO Ratio of open bubbles at grain boundary to total open porosity 00 FGG Rate of grain growth sweeping of fission gas atom is multiplied by FGG 10
RFGFAC
Multiplying factor for the FGR from rim structure RFGFACne0 when additional fission gas release from rim region is
assumed RFGFAC=0 when no additional fission gas release is asssumed
10
FRMIN Minimum fission gas release rate () 05 THEATF Interpolation parameter used in in-grain diffusion equation θ 10 FMULT Fitting factor of time step width for fission gas release model 10
NODEG Number of in-grain meshes for fission gas release model (5 or less) Restart calculation automatically takes over the value specified in
[Base-calculation] 3
RREL Dividing ratio of in-grain element to be set for each NODEG-1 in fission gas atoms diffusion calculation (designates NODEG-1 number) 50 10
RB Thickness of grain boundary layer element for re-dissolution of fission gas atoms (cm) 20times10-6
FPMOX
To simulate the FGR of MOX fuel FGR which is calculated by FGR model as usual is multiplied by FPMOX However this only hypothetically increases the amount of released gas and the calculation of fission gas atoms diffusion inside grain is not affected
10
JAEA-DataCode 2013-009
- 109 -
Name-list Input (22) Variable name Contents Default
value
IPEXT
Option for the external pressure Pext acting on grain boundary bubbles
14
IPEXT=0 Pext =0 IPEXT=1 Pext=plenum pressure IPEXT=2 Pext=contact pressure between pellet and cladding IPEXT=3 Pext= max (plenum pressure contact pressure)
IPEXT=13 Pext= thermal stress calculated by the ERL mechanical analysis taking into account the plenum gas pressure and the contact pressure
IPEXT=14 Pext= average stress obtained by stress calculation in the ERL
mechanical analysis + plenum gas pressure
Only when IPEXT=14(default) Pext is set in the following way
Here Sav is the thermal stress which is calculated by the ERL mechanical
analysis as a hydrostatic compressive stress and usually a negative value
and the contact force is automatically included in the calculation of Sav
1) When IGASP=0 Pext=-Sav+plenum gas pressure is set When Sav is
positive ie tensile stress Sav=0 is set
2) When IGASP=2 Pext= -Sav+ plenum gas pressure is set However
when -Savlt0 or when Sav is a positive tensile stress and 2 0extPrγ
+ =
holds Pext is fixed at Pext =208rγ
minus times
ISIGOP ISIGOP=1 is set when evaluating Pext by adding correction on the basis of upper limit of gas bubble strain increment 0
FSIGM Tuning parameter to multiply Pext by FSIGM 10
IFBSAT IFBSAT=1 should be designated when gas saturation concentration at grainboundary is given by a certain fixed value ie FBSATS 0
FBSATS When IFBSAT=1 saturation concentration of gas atoms at grain boundary (atomscm2) 50times1015
JAEA-DataCode 2013-009
- 110 -
Name-list Input (23) Variable name Contents Default
value
Options for rate-law FGR model (IGASP=2) HP (Effective when IGASP=2) Parameter to adjust the increasing rate of radius
of grain boundary gas bubble in its grwoing stage 10
HN (Effective when IGASP=2) Parameter to adjust the decreasing rate of radius of grain boundary gas bubble in its shrinking stage 02
FGCND (Effective when IGASP=2) Parameter to adjust the gas migration conductance from grain boundary gas bubbles 10
NFC (Effective when IGASP=2) NFC (integer) value when assuming the volume of conduit of gas percolation from grain boundary bubbles as
0 ( ) ( )c c c eV V f F g σ= and 0( ) 1 exp[ ( ) ]NFCc c cf F F F= minus minus
10
NSC (Effective when IGASP=2) NSC (integer) value when assuming the volume of conduit of gas percolation from grain boundary bubbles as
0 ( ) ( )c c c eV V f F g σ= and 0 NSC( ) 1 exp[ ( ) ]e e eg σ σ σ= minus minus 10
SIG0 (Effective when IGASP=2) Value of 0
eσ (MPa) when assuming the volume of conduit of gas percolation from grain boundary bubbles as
0 ( ) ( )c c c eV V f F g σ= and 0 NSC( ) 1 exp[ ( ) ]e e eg σ σ σ= minus minus 100
FC1 (Effective when IGASP=2) Coverage ratio 0
cF (-) of grain boundary by grain boundary gas bubbles after one-time coalescence of grain boundary bubbles
085
FC2 (Effective when IGASP=2) Coverage ratio 0
cF (-) of grain boundary by grain boundary gas bubbles after two-times coalescences of grain boundary bubbles
09
FC3 (Effective when IGASP=2) Coverage ratio 0
cF (-) of grain boundary by grain boundary gas bubbles after three-times coalescences of grain boundary bubbles
095
FC4 (Effective when IGASP=2) Coverage ratio 0
cF (-) of grain boundary by grain boundary gas bubbles after four-times coalescences of grain boundary bubbles
099
RINIT (Effective when IGASP=2) Initail radius of grain boundary bubble (microm) 001
NGB (Effective when IGASP=2) Number of bubbles which coalesce into one large bubble when grain boundary bubbles make tunnel and become open to outer space
4
MGB (Effective when IGASP=2) Maximum number of repeated coalescences of grain boundary bubbles when grain boundary bubbles make tunnel and become open to outer space
10
TMG (Effective when IGASP=2) Pellet threshold temperature (K) under which no bubble coalescence ocurrs 12000
DVLTM (Effective when IGASP=2) Lower limit of temperature referred to by the grain bopundary diffusion coefficient of vacancy 10000
LRF (Effective when IGASP=2) LRF=1 is set if the grain boundary gas bubble is assumed to stop growing at the limiting radius RF 0
FCON (Effective when IGASP=2) Threshold coverage of grain boundary bubbles on grain boundary to allow the bubble coalescence to occur 03
JAEA-DataCode 2013-009
- 111 -
Name-list Input (24) Variable name Contents Default
value
Options for pellet swelling
IFSWEL
Option for pellet swelling model =0 Chubb amp Zimmermann+FEMAXI-III =1 solid fission products swelling+ gas bubble swelling =2 MATPRO-09 =3 Kosaka =4 Studsvik =5 Hollowell
Restart calculation automatically takes over the value specified in [Base-calculation]
0
STFCP (Used when either IFSWEL = 0 or IFSWEL=5) Contact pressure above which fission gas bubble swelling does not occur
(Pa) Used in ERL mechanical analysis 30times107
SPCON (Used when either IFSWEL = 0 or IFSWEL=5) Contact pressure above which fission gas bubble swelling does not occur
(Pa) Used in 2-D local mechanical analysis -106
SWSLD
When IFSWEL=0 factor to multiply the solid fission product swelling rate 025 per 1020 fissioncm3
Restart calculation automatically takes over the value specified in [Base-calculation]
10
FDENSF
When either IFSWEL=0 or =1 option for factor fD of density decrease induced by solid fission products swelling
FDENSF=0 01=Df FDENSF=1 0
10 swsD
VfV
∆= minus
0
FACP (When IFSWEL=1) Factor to multiply the contact pressure term of the external pressure on grain boundary gas bubble 10
A1
(Used when IFSWEL = 4) Value of A1 used in the equation ΔVV()=(A1-C1FGR())BU where 0≦BU≦BU1 Restart calculation automatically takes over the value specified in
[Base-calculation]
00965
C1
(Used when IFSWEL = 4) Value of C1 used in the equation ΔVV()=(A1-C1FGR())BU 0≦BU≦BU1 Restart calculation automatically takes over the value specified in
[Base-calculation]
0000459
BU1
(Used when IFSWEL = 4) Value of BU1 (MWdkgU) used in the equation ΔVV()=(A1-C1FGR())BU 0≦BU≦BU1 Restart calculation automatically takes over the value specified in
[Base-calculation]
570
A2
(Used when IFSWEL = 4) Value of A2 used in the equation ΔVV()=(A1-C1FGR())BU1+A2(BU-BU1) BU1ltBU Restart calculation automatically takes over the value specified in [Base-calculation]
0032
JAEA-DataCode 2013-009
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Name-list Input (25) Variable name Contents Default
value
Options for densification of pellet
IDENSF
Option for equation of pellet densification =0FEMAXI-III =1Rolstad =2NRC =3Marlowe =4Halden =30 Schlemmer and Ichikawa Restart calculation automatically takes over the value specified in [Base-calculation]
0
DMAX(40)
(Used when IDENSF = 0 2 or 3) Upper limit of pellet volume shrinkage due to densification () at each axial segment Restart calculation automatically takes over the value specified in [Base-calculation]
4010
SBU
(Used when IDENSF = 0) Burnup at which 90 of densification is completed (MWdtUO2) Restart calculation automatically takes over the value specified in
[Base-calculation]
200000
TDNSF (Used when IDENSF = 1 or 3) Sintering temperature (K) Restart calculation automatically takes over the value specified in
[Base-calculation] 20000
GG (Used when IDENSF = 3) Crystal grain diameter after heat treatment (m) Restart calculation automatically takes over the value specified in
[Base-calculation] 10-5
GG0 (Used when IDENSF = 3) Initial crystal grain diameter (m) Restart calculation automatically takes over the value specified in
[Base-calculation] 80times10-6
SITIM (Used when IDENSF = 3) Heat treatment time (hr) Restart calculation automatically takes over the value specified in
[Base-calculation] 240
ADST Densification adjustment factor used when IDENSF=4 Restart calculation automatically takes over the value specified in
[Base-calculation] 06
JAEA-DataCode 2013-009
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Name-list Input (26) Variable name Contents Default
value
Options for densification and swelling of pellet
DENSWL
Option for combination model of densification and swelling =0 combination model is not used Densification and swelling are
calculated independently from each other =1 combination model is used Restart calculation automatically takes over the value specified in [Base-calculation]
0
DD1
Assuming that densification is DS(vol) and swelling is SW(vol) the combined volume change VC(vol) is assumed as
1(1 )VC D d DS D SW= minus sdot sdot + sdot where 1( DD1)d = is an adjusting factor for the maximum volumetric shrinkage DMAX
Restart calculation automatically takes over the value specified in [Base-calculation]
13
ALD
ldquoDrdquo in the above equation is given by ( )10tan [ ]
05Bu Bu
Dα
π
minus sdot minus= +
ALD is the value of α in this equation Restart calculation automatically takes over the value specified in
[Base-calculation]
04
BU0
ldquoDrdquo in the above equation is given by ( )10tan [ ]
05Bu Bu
Dα
π
minus sdot minus= +
BU0 is the value of Bu0 a reference burnup in this equation(GWdt) Restart calculation automatically takes over the value specified in [Base-calculation]
250
Options for fuel grain growth
IGRAIN Option for equation representing UO2 grain growth =0 Itoh =1 Ainscough =2 MacEwan =3 Lyons =4 MATPRO-09 =5 MATPRO-11
0
GR Initial pellet grain size (μm) Restart calculation automatically takes over the value specified in
[Base-calculation] 100
GRWF (Used when IGRAIN = 0) Grain growth rate is multiplied by GRWF 15
AG (Used when IGRAIN = 0) Fitting parameter (grain growth suppression factor) 10
JAEA-DataCode 2013-009
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Name-list Input (27) Variable name Contents Default
value
Options for fuel grain growth
IGRAIN Option for equation representing UO2 grain growth =0 Itoh =1 Ainscough =2 MacEwan =3 Lyons =4 MATPRO-09 =5 MATPRO-11
0
GR Initial pellet grain size (μm) Restart calculation automatically takes over the value specified in
[Base-calculation] 100
GRWF (Used when IGRAIN = 0) Grain growth rate is multiplied by GRWF 15
AG (Used when IGRAIN = 0) Fitting parameter (grain growth suppression factor) 10
Options for He release (Refer to [Note] in the next page) NTVHE Number of time points set by TVHE 0
TVHE(41100) TVHE(1 n) number of nth time points (hr) (mole) TVHE(i+1 n) molar amount of He generated in axial segment I at nth
time point 410000
HER
HER=1 He release rate is HERLS times as large as the FGR of Xe+Kr HER=2 option toi assume a fixed release rate ( HEC1 (Default=1000)) to the generated quantity of He irrespective of temperature and burnup HER=3 He absorption and release model
1
HERLS Multiplying factor for the ratio of He release rate to fission gas release rate (Effective when HER=1) 30
HEC1 He gas release rate is assumed as fixed at HEC1() of He generation quantity irrespective of temperature and burnup (Effective when HER=2)
1000
HEGEN (NHIST)
(Effective when HER=3) Option for specifying the time history of He generation quantity HEGEN (N) (N is history point number) is set Eg when
ldquoHEGEN(1)=12E13 HEGEN(4)=234E14rdquo are input at the first history point(initial stage) 12E13 atomscm3 and at the fourth history point 234E14 atomscm3 are designated and between these two points a linear interpolation is made with respect to time
HEGEN(1) is indispensable and initial spacial concentration in solid phase However if IHEGEN=1 is designated unit of HEGEN becomes atomsg-fuel
1500 00
IHEGEN (Effective when HER=3) IHEGEN designates unit of HEGEN IHEGEN=0 atomscm3 IHEGEN=1 atoms g-fuel 0
DHE1
(Effective when HER=3) D1 of the following He diffusion coefficient inside grain (lattice)
11 1 2exp ( ) (f )LAT
QD D f Bu fRT
= minus + +
(m2s) 8times10-7
JAEA-DataCode 2013-009
- 115 -
[Note] Explanation of absorptionrelease model of Helium in UO2 and MOX fuels
The model adopts the He generation quantity calculated by an external burning analysis
code as a function of initial composition of fuel burnup or time When HEAR=1(default=0)
this process is performed in FEMAXI-7 If HEAR=0 the calculation is not performed even if
the He quantity is input
The He generation data is fed to FEMAXI-7 by either designation by name-list parameter
HEGEN(time atomscc) or adding several data lines to the last part of input file and the code
calculates as a function of time the He generation quantity during a certain time-step ie
increment (atomscc-fuel) during the time step in each ring element of pellet
The He diffusion inside pellet is calculated by a concentration-gradient driven diffusion in
the radial direction of pellet assuming that an average concentration of He (atomscc-fuel) in
each ring element has a gradient in the radial direction of pellet Here the boundary
condition at the interface of pellet solid surface and gas phase (assuming that the He spacial
concentration is equal to that of the solid) initial spacial concentrations of He in solid and gas
phase (atomscc-fuel) are specified by input and calculation is performed with respect to
absorptionrelease of He across the pellet-gas phase in each axial segment to derive the He
concentration in gas phase and partial pressure (MPa) in whole rod including plenum space
The diffusion coefficient of He in solid has input options to specify the parameters consisting
of the equation
The solid-gas interface is basically assumed as the surface of outermost ring element of
pellet facing the gap gas (HEBDS=1) or in addition to this inner wall surface of centerhole
of pellet (HEBDS=2) On the other hand the direct absorption and release from the
designated ring elements to gas phase are taken into account That is the He concentration in
gas phase at temperature of each ring element or the He concentration in each ring element is
multiplied by factor HERFAC(I factor) where (I=1helliphellip36 0 le factor le 01 ) to calculate
the direct absorptionrelease at a certain time-step and to be reflected on the average He
concentration of each ring element in the diffusion calculation
JAEA-DataCode 2013-009
- 116 -
Name-list Input (28) Variable name Contents Default
value
QHE1
(Effective when HER=3) Q1 (calmol) of the following He diffusion coefficient inside fuel grain (lattice)
11 1 2exp ( ) (f )LAT
QD D f Bu fRT
= minus + +
460000
DLT (Effective when HER=3) Lower limit value of He diffusion coefficient inside fuel grain (lattice) (m2s)
706times10-17
DHEF1
(Effective when HER=3) 1( )f Bu (m2s) of the following He diffusion coefficient inside fuel grain (lattice)
11 1 2exp ( ) (f )LAT
QD D f Bu fRT
= minus + +
00
DHEF2
(Effective when HER=3) 2(f )f (m2s) of the following He diffusion coefficient inside fuel grain (lattice)
11 1 2exp ( ) (f )LAT
QD D f Bu fRT
= minus + +
00
NODEH
(Effective when HER=3) Number of elements inside grain in He release model (Max 50) Restart calculation automatically takes over the value specified in
[Base-calculation]
5
HESOL He solubility insolid fuel (spacial concentration atomscm3) 1027 High burnup (rim) structure model
HBS
HBS=0 high burnup model is not used HBS=1JAEA rim model with local burnup HBS=2 JAEA rim model with effective burnup
Effective burnup neffB (GWdtM) is defined as
11 0exp ( )n n n
eff eff nB B k T T t Bminus= sdot minus minus sdot ∆ + ∆
where neffB effective burnup at n-th time step (GWdtU)
nT local fuel temperature (K) at n-th time step This is assumed as
0nT T= when 0nT Tle
0T Reference temperature (K)
1k constant
t∆ time step increment (s) nB∆ burnup increment at n-th time step Restart calculation automatically takes over the value specified in [Base-calculation]
0
TSTD (Used when HBS=2) Reference temperature 0T (K) in calculating effective burnup
10000
KON1 (Used when HBS=2) A constant 1k to multiply the temperature dependent term of effective burnup
10-8
JAEA-DataCode 2013-009
- 117 -
Name-list Input (29) Variable name Contents Default
value
FPINF
(Used when HBS=1 or 2) Lassmann empirical model is applied to fission gas transfer from rim structure to pore Ratio FPOR of amount of gas transferred from solid matrix to the free space outside pellet to the total amount of fission gas atoms generated in the rim structure is expressed as a function of burnup Bu ( localBu or effB ) Here FPNF(wt) is used in the function as
( ) ( )( )1 0wt =FPINF+(GEN1times -FPINF)timesexp -GEN2times -Xe Bu Bu Bu
[ ]1FPOR Total Xe generation(Wt)= Xe
[ ]Total generation(wt) 00145 (GWdt)= sdotXe Bu
025
GEN1 (Used when HBS=1 or 2) Value of 1Gen in the above equation (wtGWdt) 00145
GEN2 (Used when HBS=1 or 2) Value of 2Gen in the above equation 01 BURMXE (Used when HBS=1 or 2) Value of Bu0 in the above equation (GWdt) 600
BKONA (Effective when HBS=1) Burnup at which rim structure transformation begins (GWdtU) 650
ARIM
(Effective when HBS=2) Value of α in the following equation assuming that the transformation ratio into rim structure is Xv
( )11tan
Xv effB Buα δ
π
minus minus= +
105
BURIMS (Effective when HBS=2) Value of 1Bu (GWdt) in the equation defining Xv the ratio of transformation into rim structure
600
DRIM (Effective when HBS=2) Value of δ in the equation defining Xv the ratio of transformation into rim structure
052
RMOGR
Option to specify the additional amount of FGR from the gas pores in the rim structure RMOGR=0 no additional FGR from the gas pores
RMOGR=1 additional FGR is evaluated assuming OPR=ATHMR where OPR is the fraction of open pores and 0 OPR ATHMR FPORle = le That is after the rim structure is formed OPR fraction of fission gas atoms generated in the rim structure is released to external space
RMOGR=2 open pore fraction OPR to the rim pore porosity rimp is given
as a function of rimp
003OPR (0 023)023 rim rimp p= sdot le le
( )( ) ( )OPR 003 015 003 100 23 023 024rim rimp p= + minus sdot minus le le
( )( ) ( )OPR 015 045 015 100 24 024 025rim rimp p= + minus sdot minus le le
1
JAEA-DataCode 2013-009
- 118 -
Name-list Input (30) Variable name Contents Default
value
ATHMR (Effective when RMOGR=1) Fraction of athermal release of gas (-) 00
RIMPRO (Used when HBSgt0) Option for pellet rim structure thermal conductivity model =0 Ikatsu model =1 Billaux model
0
BXEQ (Used when HBSgt0) The equivalent burnup Bx to calculate the thermal conductivity of the rim structure region (GWdtU) 400
RIMSWL
(Used when HBSgt0) Option for the swelling of the rim structure region When RIMSWL=1 the volumetric swelling rate of the rim structure region is assumed equal to [porosity + solid swelling] irrespective of the value of IFSWEL Restart calculation automatically takes over the value specified in [Base-calculation]
0
RMPST
Option for calculation of rim structure porosity rimP
RMPST=0 the porosity is not calculated but fixed at 050=rimP RMPST=1 NFD empirical corelation equation is used
Porosity in rim structure RMPOR() is defined as RMPOR = PORMAX (1- PG4)+PORMIN PG4sdot sdot
PORMAX = ( ) 221 2 PGBuBuPG +minussdot
PORMIN = ( ) 223 2 PGBuBuPG +minussdot where rimP =RMPORtimes001 and maximum value of rimP is assumed
as PMX RMPST=2Billaux model is used
tMGWdBPBuAPBPAPprim 1211 ltminussdot=
AP1 AP2 BP1 BP2 GWdtM= sdot minus le lerimp Bu Bu
PMX BP2 GWdtM= gtrimp Bu
Bu local burnup ( localBu or effB ) (GWdtM)
1
PG1 PG1 value ( (GWdtM)2) when RMPST=1 0005 PG2 PG2 value ( (GWdtM)2) when RMPST=1 25 PG3 PG3 value ( (GWdtM)2) when RMPST=1 00013 PG4 PG4 value (-) when RMPST=1 05 BUPOR BU2 value (GWdtM) when RMPST=1 400 AP1 AP1 value (GWdtM)-1 when RMPST=2 00024 AP2 AP2 value (-) when RMPST=2 0106 BP1 BP1 value (-) when RMPST=2 650 BP2 BP2 value (GWdtM ) when RMPST=2 1500 PMX When RMPST=1 or 2 maximum value of rimstructure porosity (-) 0254
JAEA-DataCode 2013-009
- 119 -
Name-list Input (31) Variable name Contents Default
value
Youngrsquos modulus option
IPLYG Option for equation of pellet Youngrsquos modulus
=1 MATPRO-09 =2 MATPRO-11 =30 MATPRO-11 2
FPYG Multiplying factor for pellet Youngrsquos modulus 10
IZYG Option for cladding Youngrsquos modulus =1 Fisher =2 MATPRO-A and -11 =41SUS304
2
FCYG Multiplying factor for cladding Youngrsquos modulus 10
CYNG Cladding Youngrsquos modulus is specified by input CYNG (Pa) If CYNG(gt0) is specified by input the Youngrsquos modulus is fixed at CYNG (Pa) 00
Poissonrsquos ratio option
IPOIS Option for pellet Poissonrsquos ratio =1 MATPRO-09 =30 MATPRO-11 =31 Nutt and Yamada
1
ICPOIS Option for cladding Poissonrsquos ratio =1 Fisher =40SUS316 =41SUS304
1
CPOIS Cladding Poissonrsquos ratio is specified by input CPOIS (-) If CPOIS(gt0) is specified by input the Poissonrsquos ratio is fixed at CPOIS 00
Thermal expansion option
IPTHEX
Option for pellet thermal expansion rate =0 or =1 MATPRO-09 =2 Burdick =3 Halden =4 Conway and Fincel =5 MATPRO-A =6 Martin
=30 MATPRO-11 =31 Martin and Tokar =32 MATPRO-A
0
FPTM Multiplying factor for pellet thermal expansion rate 10
ICATHX Option for cladding thermal expansion rate
=0 MATPRO-09 =1 Scott =2 MATPRO-A =3 MATPRO-11 =40SUS316 =41SUS304
0
ATHEX Thermal expansion coefficient of cladding in the axial direction (oC-1) (Used when ICATHX=0)
4441 times10-6
RTHEX Thermal expansion coefficient of cladding in the radial direction (oC-1) (Used when ICATHX=0)
6721 times10-6
OXTHM Option for thermal expansion rate of cladding oxide layer =1 MATPRO-A (ZrO2) =41SUS-304 =43 SUS316 1
FCTM Multiplying factor for cladding thermal expansion rate 10
JAEA-DataCode 2013-009
- 120 -
Name-list Input (32) Variable name Contents Default
value
Pellet crackrelocation option FRELOC Relocation parameter 05 EPSRLZ Relocation strain in the axial direction 0003
FACR It is assumed that pellet recovers its stiffness if crack space shrinks by FACR times the relocation strain in the radial direction 10
FACZ It is assumed that pellet recovers its stiffness if crack space shrinks by FACZ times the relocation strain in the axial direction 10
IURS When IURS=1 ε R which is assumed as the strain to recover completely the pellet stiffness includes gas bubble swelling and creep strains
0
IYNG Option for pellet crack model (mechanical model)
=0 sstiffness recovery is approximated by a quadratic function =1 by a linear function
1
ECRAC3 Pellet stiffness when pellet is completely cracked (Pa) (mechanical model) 20times109
EFAC Fraction of stiffness recovery of cracked pellet to the pellet Youngrsquos modulus (ERL mechanical analysis) 01
SIGFL Critical stresses PCθσ (MPa) of pellet fracture in the circumferential
direction The same value is applied to those in the radial and axial directions
100
DELTAR (NAX NHIST)
Adjustment quantity (microm) of thermal relocation of pellet of each axial segmentat at arbitrary history points
Assuming that the gap size is GAPi as a result of mechanical analysis at
history point ldquoi-steprdquo the thermal gap size GAP1i is given by
GAP1i=GAPi - Σi(DELTAR)
Here Σi(DELTAR) is the accumulated value of DELTAR until i-step (DefaultDELTAR(IZ IN)=0 (1 le IZ le NAX 1 le IN le NHIST)) However when the gap size comes to GAP1i= GAPi - Σi(DELTAR)=0 GAP1=0 is assumed even if DELTARgt0is designated after the i-step
Also Σi(DELTAR) is reset to null at the moment PCMI ocurrs in the mechanical analysis Σi(DELTAR)=0 is assumed even if DELTARgt0 is specified at the history points after the step at which gap reopens
All 00
Creep option
IPCRP
Option for pellet creep equation =1 MATPRO-09 =2 MATPRO-11 =4SKI model for UO2
=5 Halden UO2 Creep model =11 SKI-based MOX model (fH=1) =12 SKI-based MOX model (fH=2) =13 SKI-based MOX model (fH=3) =15 Halden MOX Creep model =30 MATPRO-11 (MOX)
4
FCRFAC Magnification factor for pellet creep equation in mechanical model 10
TCS Cut-off value of temperature in pellet creep calculation (K) in mechanical model 127315
JAEA-DataCode 2013-009
- 121 -
Name-list Input (33)
Variable name Contents Default value
CRFAC Magnification factor for cladding creep rate (mechanical analysis) 10
TCCS Upper cutoff temperature in cladding creep calculation (K) (mechanical analysis) 107315
FAIMAX Maximum limit value of fast neutron flux used in cladding corrosion calculation (ncm2s) common to thermal and mechanical analyses 1015
SIGMAX Upper cutoff value of equivalent stress (Pa) in cladding creep calculation (mechanical analysis) 4times108
CRPEQ
Option for cladding creep model =0 MATPRO-09 =1 Nen-an-sen =2Franklin
=3 McGrath(Halden) =40SUS316 =41SUS304 =43 SUS316(MRI)
3
HTCRP Option for cladding high temperature creep =1 Rosinger =20 Donaldson(Westinghouse) =21 Donaldson(Wolverine) =22 Donaldson(Sandvik (NRU))
1
HTCREP When high temperature creep model of cladding is used irrespective of temperature condition HTCRP=1 is to be designated 0
ICRP
When ICRP=0 out of the two creep equations ie one designated by CRPEQ and the other designated by HTCRP one equation which gives a faster creep rate than the other is used in calculation When ICRP=1 for the temperature under CRTEMP the equation designated by CRPEQ is used and over CRTEMP the other one designated by HTCRP is used
0
CRTEMP Temperature (oC) at which creep equation of Zircaloy is shifted from the one designated by CRPEQ to high temperature creep equation designated by HTCRP (Effective when ICRP=1)
4500
THETC Implicit solution parameter θ used in creep analysis ( 0 1θle le ) 10
IPUGH =1 Pughrsquos reversal method is adopted in the cladding creep calculation in
2-D local mechanical analysis =0Pughrsquos reversal method is not adopted
1
IPUGH2 =1 Pughrsquos method is adopted in the cladding creep calculation in ERL
mechanical analysis =0Pughrsquos reversal method is not adopted
0
ICC
Option for creep strain increment calculation ICC=0 creep strain increment is calculated by the creep rate with an
updated stress 11
11
+++
++ ∆=∆ ic
nnic
n t θεε ICC=1 creep strain increment is calculated by adding a correcting term
derived from updated stress to the approximated value at i-th step [ ] 1
1
11
1++++
++ +∆=∆ i
nic
nic
nic
n dC σεε θ
0
JAEA-DataCode 2013-009
- 122 -
Name-list Input (34) Variable name Contents Default
value
Plasticity option IFY Pellet plasticity model option =0 Rodford =1 Tachibana 1 FYIEF Option to multiply pellet yield stress by FYIEF 10
ICPLAS
Option for cladding stress-strain relationship =1 FEMAXI-III =2 MATPRO-11 =3 modified MATPRO-11 =4 Ohta model for PWR cladding =5 Ohta model for BWR cladding
=6 FRAPCON34 model =41SUS304
1
CWK (Effective when ICPLAS=2 or 3) Effective cold-work for strength coefficient K
(dimensionless cross section area) 00
CWN (Effective when ICPLAS=2 or 3) Effective cold-work for strain hardening exponent (cross sectional reduction ratio)
00
CW_INIT (Effective when ICPLAS=6) Initial value of effective cold-work (dimensionless cross section area) 05
IPLANT
Option to designate reactor type (Used when ICPLAS=6) =1HBWR(Zry-2) =2BWR(Zry-2) =3PWR(Zry-4) K(Zry) = 10 for Zry-4 K(Zry) =1305 for Zry-2 n(Zry) = 10 for Zry-4 n(Zry) = 16 for Zry-2
2
KF (Effective when ICPLAS= 3) Parameter to adjust the increment of K with burnup 10
ISTR Size K of yield curved surface of Zircaloy is assumed as 23344 (kgmm )YK σ= + when ISTRne0 0
FCYD Multiplying factor for cladding yield stress (except the Zr liner) 10
FCYDZR Multiplying factor for yield stress of cladding Zr liner 10
FCRN Multiplying factor for strain hardening exponent of cladding Zr liner 80
ISTRES
1) When ISTRES=1 (default) as per usual in FEMAXI-7 yielding of cladding and pellet is judged by equivalent stress
2) ISTRES=2 for cladding Eqs(1) and (2) are applied For pellet as per usual model of FEMAXI-7
3) ISTRES=3 for both cladding and pellet Eqs(1) and (2) are applied Eq(1) max STFACS σ= timesY Eq(2) eq maxh h ( )Sσprime = times
where maxS the largest stress of the principal stresses ( hoop stress
for cladding) σ Y yield stress eqσ equivalent stress
hprime yield function in the cases 1) 2) and 3) h yield function in the case 1)
1
STFAC
Relationship between maxS (largest principal stress) andσ Y (yield stress)
(above Eq(1)) where10 STFAC 115( 2 3)le le cong When STFACgt1 STFAC=1 is set and when STFAC ge 115 STFAC=115 is set
10
ISYD Option for strain rate dependence of yield stress
ISYD=1 strain rate dependence is taken into account ISYD=0 strain rate dependence is not taken into account
1
JAEA-DataCode 2013-009
- 123 -
Name-list Input (35) Parameters for Ohta model Parameter name Contents
PL1 Parameters for strength coefficient K
Parameter L1 of strength coefficient K Default value=1745 PL2 L2 Default value=2517 PL3 L3 Default value=526 PL4 L4 Default value=0748 PA1 A 1 Default value=3041233371times104 PA2 A 2 Default value=-8285933869times101 PA3 A 3 Default value=7490958541times10-2 PA4 A 4 Default value=-2242589096times10-5 PB1 B 1 Default value=33282432times102 PB2 B 2 Default value=298027653 PB3 B 3 Default value=-681286681times10-3 PB4 B 4 Default value=351229783times10-6 PH1 H 1 Default value=1times10-6 PH2 H 2 Default value=8775 PH3 H 3 Default value=8663 PH4 H 4 Default value=0341566 BL1 L1 Default value=1201 BL2 L2 Default value=2508 BL3 L3 Default value=1119 BL4 L4 Default value=0627 BA1 A 1 Default value=3656432405times104 BA2 A 2 Default value=-1361626514times102 BA3 A 3 Default value=1695545314times10-1 BA4 A 4 Default value=-7055897451times10-5 BA5 A 5 Default value=-3338799880times104 BA6 A 6 Default value=1330276514times102 BB1 B 1 Default value=-3617377246times104 BB2 B 2 Default value=1361156965times102 BB3 B 3 Default value=-1636731582times10-1 BB4 B 4 Default value=6386789409times10-5 BH1 H 1 Default value=1times10-6 BH2 H 2 Default value=4772 BH3 H 3 Default value=9740 BH4 H 4 Default value=5267783
PNC1 Parameters
for strain hardening exponent n
C 1 Default value=0213 PNC2 C 2 Default value=1808times10-4 PNC3 C 3 Default value=34708518times10-2 PNC4 C 4 Default value=49565251times10-4 PNC5 C 5 Default value=-50245302times10-7 PNC6 C 6 Default value=0027908
PA5 Parameters
for strain rate sensitivity exponent m
A 5 Default value=2063172161times101 PA6 A 6 Default value=-770455times10-2 PA7 A 7 Default value=9504843times10-5 PA8 A 8 Default value =-386096times10-8 PA9 A 9 Default value=-647times10-2
PA10 A 10 Default value0=2203times10-4
JAEA-DataCode 2013-009
- 124 -
Name-list Input (36) Variable name Contents Default
value
Pellet hot-press option BETAX Pellet hot press parameter α (in mechanical analysis) 0002
IHOT
This is effective in the entire-rod-length mechanical analysis model When IHOT=0 the pellet hot-press parameter is the same as the value of
BETAX When IHOT=1 the pellet hot-press parameter is given by
( )( )0
1 (1 )1 (1 )
s
s
D DD D
minus minus minusminus minus minus
BETAX
Here Dpellet theoretical density ratio(-) D0initial value of D Ds FDENH
0
IHPOP
This is effective in the local mechanical analysis model When IHOT=0 the pellet hot-press parameter α is 0 during non-contact
state and during contact state α is set equal to BETAX When IHOT=1 the pellet hot-press parameter is given by
( )( )0
1 (1 )1 (1 )
s
s
D DD D
minus minus minusminus minus minus
BETAX
Here Dpellet theoretical density ratio(-) D0initial value of D Ds FDENH
0
FDENH Ds in the equation above the maximum relative density of pellet attainable by hot-press Effective when IHOT=1 or IHPOP=1 10
Anisotropy parameter option H0(4) Anisotropy factor H0
(H0(1) fuel pellet H0(2)Zry(or SUS) H0(3) pure-Zr H0(4)ZrO2) 410
F0(4) Anisotropy factor F0
(F0(1) fuel pellet F0(2)Zry(or SUS) F0(3)pure-Zr F0(4)ZrO2) 410
G0(4) Anisotropy factor G0
(G0(1) fuel pellet G0(2)Zry(or SUS) G0(3)pure-Zr G0(4)ZrO2) 410
Pellet dishchamfer (buffer element) model option
IDSELM When IDSELM=0 elements for dish (chamfer) space are not used in the
ERLmechanical analysis geometry When IDSELM=1 they are used
0
BUFSP Percentage of the axial length of elements for dish (chamfer) space to the axial length of pellet-pellet gap () 10
Bonding model option
IBOND
Option for P-C bonding model (mechanical model) =0 model of mechanical bonding is not applied
=1 model of mechanical bonding is applied =2 during the mechanical analysis when [gap size]=[cladding inner
diameter]-[pellet outer diameter]gt0 and the gap opens the mechanical bonding model is cancelled and the axial displacement of pellet is allowed to be independent from that of cladding When the gap is closed again ie when the cladding inner diameter becomes equal to pellet outer diameter the model of mechanical bonding is applied again Namely the displacement of pellet outer surface in the axial direction is forced to be shared with that of the cladding inner surface
0
JAEA-DataCode 2013-009
- 125 -
Name-list Input (37) Variable name Contents Default
value
SBONDG A parameterθ for adjusting the gap conductance at bonding (thermal analysis)
001
ALBD An adjustment parameter α used when the gap is open in a segment in which bonding developed (applied to the gap thermal conductance model) 07
FBONDG A parameter F for adjusting gap conductance during bonding (applied to the gap thermal conductance model) 100
BDX A parameter for determining the maximum value of the extent of bonding
advancement (hour-MPa) (common in the gap thermal conductance model and mechanical bonding model)
1000000
BDTR
The value showing the advancement of bonding under the anchored state in the axial direction regardless of the presence or absence of contact due to the advancement of bonding or contacting pressure (common in the gap thermal conductance model and mechanical bonding model)
05
PN Option for PDOWN and PUP Effective when IBOND=1
=0 PDOWN and PUP do not become effective =1 PDOWN and PUP are effective
0
PDOWN
When the power decreases during the bonding state in the segment in which its contact pressure decreases below a certain threshold value the use of bonding is terminated and a regular ldquoanchor-sliderdquo evaluation is used Effective only when PDOWNgt0 (Pa) (in the mechanical analysis model)
00
PUP
When the power increases in the segment subjected to bonding conditions in the segment in which the contact pressure exceeds a certain threshold value the bonding is terminated and a regular ldquoanchor-sliderdquo evaluation is used Effective only when PUPgt0 (Pa) (in the mechanical analysis model)
00
Cladding irradiation growth option
ICAGRW
Cladding irradiation growth equation option = 0 irradiation growth is not applied =1 MATPRO-09 = 2 Manzel = 3 Hannerz = 4 Hesketh =41 SUS304 =43SUS316 Restart calculation automatically takes over the value specified in
[Base-calculation]
1
CATEXF (Used when ICAGRW = 1) Factor in the axial direction f Z Restart calculation automatically takes over the value specified in
[Base-calculation] 005
COLDW (Used when ICAGRW = 1) Cold work CW Restart calculation automatically takes over the value specified in
[Base-calculation] 081
RX Multiplying factor for irradiation growth of cladding oxide layer Restart calculation automatically takes over the value specified in
[Base-calculation] 10
JAEA-DataCode 2013-009
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Name-list Input (38)
Variable name Contents Default value
Gas flow model option
IST
Option for internal gas flow See section 413 for detail =0 model of gas diffusion in the axial direction is applied
=1 model of instantaneous pressure equilibrium and complete mixture of gas
=3 model of gas isolation in each segment
1
GPCPR When IST=3 pellet-cladding contact pressure (MPa) at which conditions of no gas flow in the axial direction are set 100
BDTR2 When IST=3 bonding progress (-) at which conditions of no gas flow in the axial direction are set 09
GMIN Minimum value (cm) of gap width for the gap gas flow model 0001
THG1 Interpolation parameter θ1 of temperature and volume etc of gas Used in
the model of fission gas flow in the axial direction 10
THG2 Interpolation parameterθ 2 used in diffusion calculation of model of fission
gas flow in the axial direction 10
Cladding oxidation model option
ICORRO
Cladding outer surface corrosion model option =0 not considered =1 EPRI =2 MATPRO-A(PWR)
=3 MATPRO-A(BWR) =4NUPEC =6 NUREG-CR-7022 (Zircloy-4 in PWR condition) =7 NUREG-CR-7022 (M5 alloy in PWR condition) =8 NUREG-CR-7022 (ZIRLO in PWR condition) =9 NUREG-CR-7022 (Zircaloy-2 in BWR condition)
1
RCORRO Oxide layer growth adjustment factor to multiply the oxide layer growth rate by RCORRO 10
FCORRO Factor to increase the oxide layer growth rate Multiplication =(10+FCORRO) 00
PBR Piling-Bedworth ratio = volume expansion ratio of oxide to metal in Zircaloy Piling-Bedworth Ratio 156
PX Portion of volume expansion ratio X in the radial direction () where X=PBR-10 This volume expansion is due to oxidation 800
OXFAC Multiplying factor for the oxide thermal conductivity 10 OXTHMX Upper limit of oxide layer thickness in calculation (microm) 1000
OXTH(41) Initial oxide thickness of cladding outer surface at each axial segment (microm) Restart calculation automatically takes over the value specified in [Base-calculation]
4101
CNOX CNOX(microm-1) specifies the multiplying factor F for the equation of oxide thermal conductivity F=1-CNOXS where S is oxide thickness (microm) 00
JAEA-DataCode 2013-009
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Name-list Input (39) Variable name Contents Default
value Dry-out experiment analysis option
IDRY Option for Dry-out analysis When IDRY=1 dry-out analysis is On 0
DII Inner diameter of inner tube (cm) 18
DIO Outer diameter of inner tube (cm) 20
DOI Inner diameter of outer tube (cm) 21
DOO Outer diameter of outer tube (cm) 23
DSI Inner diameter of capsule outer mantle (cm) 27
DSO Outer diameter of capsule outer mantle (cm) 32
T1IN Inlet temperature of heating steam (oC) 2900
T5IN Inlet temperature of circulating water (oC) 500
TBOUND Coolant water temperature (oC) 400
PRS1 Pressure of heating steam (MPa) 72
PRS3 Pressure of He layer (MPa) 01
PRS5 Pressure of circulating water (MPa) 72
V1 Flow velocity of heating steam (ms) 02
V2 Flow velocity of circulating water (ms) 001
FTH Adjustment factor for the thermal conductivity of He layer (-) 10
RHC Adjustment factor for the thermal conductivity of heating steam layer and for radiative heat transfer coefficient of circulating water (-) 10
DTDRY Maximum time step width in calculating temperatures in dry-out analysis (s) 01
IV1 When IV1=1 mass flow rates (kgs) of heating steam and circulating water are set equal and input of VI is ineffective 0
JAEA-DataCode 2013-009
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Name-list Input (40) Variable name Contents Default
value
Numerical output and plotted figure output option
IPHIS
Option for summary output For the history point designated by IP=1 numerical output is given in detail In addition summary output is given for each calculated quantity as a function of time
IPHIS=0 summary output is given only for the history point designated by IP=1 IPHIS=1 summary output is given for all the history points irrespective of IP
0
IPRINT Output option (=0 no output =1 output) (1) Input data list 1 (2) Fuel design data 0 (3) Mesh coordinates data 0 (4) List of parameters 0 (5) History data 1 (6) Results of thermal analysis of each time step 1 (7) Results of mechanical analysis of each time step 1 (8) Summary of thermal analysis results for each segment (thermal analysis) 1 (9) Summary of mechanical analysis results for each segment (thermal analysis) 1 (10) Summary of fission gas release results for each segment (thermal analysis) 1 (11) Summary of fission gas release results for entire fuel rod (thermal analysis) 1
(12) Summary of deformation behavior of pelletcladding of each segment (mechanical model) 1
(13) Summary of pellet stress and strain of each segment (mechanical analysis) 1 (14) Summary of cladding stress-strain of each segment (mechanical analysis) 1 (15) Summary of major results (final information) 1 (16) Output of He generation quantity at each segment 0
(17) Output of relative power density profile in the radial direction of pellet stack at each axialsegment 0
(18) Output of relative power at each axial segment 0 (19) Summary of entire-fuel-rod strain and corrosion of the objective segment 1 (20) Summary of coolant and of cladding oxidation (thermal analysis) 0 (21) INDO table shown after the summary output 0
(22) Table of plotted history points shwon after IDNO table 0
JAEA-DataCode 2013-009
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Name-list Input (41) Variable name Contents Default
value
IWNOD
Segment output option (= 0 no output = 1 output) For IPRINT(8) IPRINT(9) IPRINT(10) IPRINT(16) IPRINT(17) output
(including plotter output) is performed for segment I where IWNOD(I) = 1 and output is not performed for segment I where IWNOD(I) = 0 However if all IWNOD is 0 IWNOD(IFEM) = 1 is set only at segment
IFEM
400
IWTHE Thermal analysis output option (= 0 no output = 1 output) (Option when IPRINT(6) = 1)
(1) Fuel temperature 1
(2) Gap gas 0
(3) Grain radius 0
(4) Intra-grain gas bubble radius 0
(5) Intra-grain gas bubble density 0
(6) Intra-grain gas diffusion coefficient 0
(7) Intra-grain gas effective diffusion coefficient 0
(8) Number of gas atoms in grain 0
(9) Number of gas atoms at grain boundary 0
(10) Number of gas atoms released 0
(11) Number of gas atoms in grain and at grain boundary 0
(12) Number of gas atoms released in grain and at grain boundary 0
(13) Number of gas atoms generated 0
(14) Fission gas release rate 1
(15) Gas density at grain boundary 0
(16) Saturated gas density at grain boundary 0
(17) Average stress at grain boundary 0
(18) Burn-up 1
(19) Conditions for thermal calculation 1
(20) Representative output for thermal calculation 1
(21) Number of fission gas atoms solved in solid matrix UO2 0
(22) Number of fission gas atoms in intra-grain bubbles 0
(23) Radius of inter-grain gas bubble 0
(24) Gas-release threshold radius of inter-grain bubble 0
(25) Fraction of coverage on grain boundary by inter-grain bubbles 0
(26) Threshold fraction of coverage on grain boundary by inter-grain bubbles
0
(27) Number density of inter-grain gas bubbles 0 (28) Effective burnup 0 (29) Ratio of rim structure formation ( vX ratio) 0 (30) Porosity in rim structure and total porosity 0
JAEA-DataCode 2013-009
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Name-list Input (42) Variable name Contents Default
value
IWFEM Output option for the Local Mechanical Analysis II (effective only when IFEMRD = 0) (= 0 no output = 1 output) (option used when IPRINT(7) = 1)
(1) Stress in the radial direction 0 (2) Stress in the axial direction 1 (3) Stress in the circumferential direction 1 (4) Shear stress 0 (5) Equivalent stress 1 (6) Yield stress 0 (7) Total strain in the radial direction 0 (8) Total strain in the axial direction 0 (9) Total strain in the circumferential direction 0 (10) Total shear strain 0 (11) Equivalent plastic strain 1 (12) Creep strain in the radial direction 0 (13) Creep strain in the axial direction 0 (14) Creep strain in the circumferential direction 1 (15) Shear creep strain 0 (16) Equivalent creep strain 0 (17) Elastic strain in the radial direction 0 (18) Elastic strain in the axial direction 0 (19) Elastic strain in the circumferential direction 0 (20) Shear elastic strain 0 (21) Thermal strain in the radial direction 0 (22) Thermal strain in the axial direction 0 (23) Densification strain 0 (24) Swelling strain 0 (25) Stiffness in the radial direction 0 (26) Stiffness in the axial direction 0 (27) Stiffness in the circumferential direction 0 (28) Creep rate in the radial direction 0 (29) Creep rate in the axial direction 0 (30) Creep rate in the circumferential direction 0 (31) Creep rate in the shear direction 0 (32) Equivalent creep rate 0 (33) Total strain rate in the radial direction 0 (34) Total strain rate in the axial direction 0 (35) Total strain rate in the circumferential direction 0 (36) Total strain rate in the shear direction 0 (37) Equivalent total strain rate 0 (38) Strain energy 0 (39) Temperature distribution in the radial direction 1 (40) Mechanical interaction between pelletcladding 1
JAEA-DataCode 2013-009
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Name-list Input (43) Variable name Contents Default
value
IWFEM (continued)
Output option for the Local Mechanical Analysis II (effective only when IFEMRD = 0) (= 0 no output = 1 output) (option used when IPRINT(7) = 1)
(41) Mechanical interaction between pelletpellet 1 (42) Displacement of node 1 (43) Plot of ldquoPellet-Clad Mechanical Interactionrdquo 1 (44) Crack yielding map 1 (45) Mechanical calculation conditions 1
IWROD Output option for the Entire-Rod-Length Mechanical Analysis I (effective only when IFEMRD = 1) (= 0 no output = 1 output)
(This option is used when IPRINT(7) = 1)
(1) Stress in the radial direction 0 (2) Stress in the axial direction 0 (3) Stress in the circumferential direction 0 (4) Equivalent stress 0 (5) Yield stress 0 (6) Creep strain in the radial direction 0 (7) Creep strain in the axial direction 0 (8) Creep strain in the circumferential direction 0 (9) Creep hardening strain 0 (10) Equivalent plastic strain 0 (11) Swelling strain 1 (12) Total strain in the radial direction 0 (13) Total strain in the axial direction 0 (14) Total strain in the circumferential direction 0 (15) Thermal strain 0 (16) Temperature of element 0 (17) Pressure in the radial and axial directions 0 (18) Displacement in the radial and axial directions 1 (19) Elastic strain 0 (20) Relocation strain of pellet 0
JAEA-DataCode 2013-009
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Name-list Input (44) Variable name Contents Default
value
MAVE
MAVE=1 average values of stress and strain obtained by ERL mechanical analysis of cladding in the radial direction are output as summary for each time step
MAVE=0 summary of stress and strain at the inner surface of cladding are output as usual
0
IFT90 Option for temperature used in PTEMP and to make a file of gap conductance The file is generated when IFT90=1 (Unit 90) 0
IWRIM Option for output of EXCEL file of rim structure model (Unit 17) IWRIM=0 output is Off IWRIM=1 output is On 0
IOUT18 Option to make Unit 18 (file of contour map of stress-strain ) IOUT18=0 file is not made IOUT18=1 file is made 0
IOUT20 Option to make Unit 20 (summary output file organizing the maximum values of calculated temperature etc ) IOUT20=0 file is not made IOUT20=1 file is made
0
IPLT Generation of FEMAXI-7 plotter data file (Unit 1)
When IPLT=0 no plotter data file is generated 1
IPLTB Format of plotter data file (Unit 1) IPLTB =0 binary format IPLTB =1 text format 0
IPLOPT
Option for the file of plotter output at time-steps =0 Calculated results are output to plotter file only at the designated
historical points of input
=1 gt1 Calculated results are output to plotter file at all the time steps
= -n ( 011 nene nn ) Calculated results are output to plotter file at every n time steps However in addition to this results are output to plotter file also at the designated historical points of input
= -1 calculated results are output at time steps exceeding DT_OUT except
at the input-designated history points = -10 calculated results are output at all the time steps from PLTIME(1) to
PLTIME(2) However results are always output at the designated historical points of input
0
DT_OUT Effective when IPLOPT= -1 Maximum interval time (hour) of plotter output which determines the interval time of plotting at the instants which are not specified by input history points
00
IWRES Option to output the summary of file contents taken over from FEMAXI calculation =0 no output =1 simplified output =2 detailed output 0
ITIM(2)
ITIM(1) is the history point number with which the plotter output file begins to be generated
ITIM(2) is the history point number with which the plotter output file is terminated
1 2000
JAEA-DataCode 2013-009
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Name-list Input (45) Variable name Contents Default value
IDNO(800)
Index data of plotter data file When IZERO=0 IDNO(401) - IDNO(500) are set 0
IDNO(1) - IDNO(40) data as a function of time and burnup 61 0 1 30
1 20 21 240
IDNO(41) - IDNO(100) data as a function of time burnup and
axial position
21 20 1 30 21 20
1 0 1 30 1 40 71
30 1 260
IDNO(101) - IDNO(300) data as a function of time burnup and
axial and radial positions (in the entire length mechanical analysis)
51 0 1 380 1 30
1 20 1 60 1 0 1 30 1 20 111
1210
IDNO(301) - IDNO(400) data as a function of time burnup and
axial and radial positions (in the local mechanical analysis)
61 140 71 230 151350
IDNO(401) - IDNO(420) Zero-power data as a function of time and burnup 61140
IDNO(421) - IDNO(450) data as a function of time burnup and radial and axial positions at Zero Power condition 71 230
IDNO(451) - IDNO(500) Zero-power data as a function of time burnup and axial and radial positions 151 350
IDNO(501) - IDNO(800) data ata as a function of time burnup and axial and radial positions 3000
44 Plot data index IDNO IDNO(1) to IDNO(600) are index for the plotter file When IDNO(K)=0 is designated for
the K-th physical quantity shown in ldquoTables (1) - (XX) Physical Quantities of Y axis (1) -
(XX)rdquo which is shown in section A5 the calculated value for the K-th physical quantity is not
stored in the plotter data file when IDNO(K)=1 it is stored and can be output in graphics
45 Calculated physical quantities in ZERO power state In the analysis of fuel behavior sometimes it is required to obtain such data as net FGR
and net permanent deformation of cladding during on-power period while eliminating the
temperature-related factors such as thermal expansion To realize this an optional function
to calculate fuel states under ZERO power state (shut-down state) and output the data is
included This function calculates the change of such quantities under zero-power state as
internal pressure space volume and cladding dimension in a calculation along the power
history by designating the name-list parameter IZERO as 1 2 3 or 4 In addition when
IZERO is designated graphic output for zero-power state can be given
JAEA-DataCode 2013-009
- 134 -
46 Method to input history point data Here the method of production of history data (line numbers 10-11) of the input file is explained
461 Power history data The following items must be inputted as the power history data
A1 = time (hr) B1=burnup A2 = linear heat rate (Wcm) A5 = fast neutron flux (ncm2sdots)
A3 = coolant temperature (K) A4 = coolant pressure (MPa) IT = input generator IP = output
option IS = temperature calculation option A6 = coolant velocity (ms)
However since B1 (burnup) is determined by input of A1 (time) and vice versa either A1
or B1 should be input The unit of B1 is designated by IBUNP when IBUNP = 0 B1 is
MWdt-UO2 when IBUNP = 1 B1 is MWdt-U and when IBUNP = 2 B1 is GJkg-U
Using IT (input generator) input by incremental form is possible IT is selected from
among 0 100 and minus100 when IT = 0 is set A1 (or B1) is recognized as a time increment
from the previous history point (or burnup increment) when IT = 100 A1 (or B1) is
recognized as the time increment from the first history point (or burnup increment) IP is an
output option IP ge 1 designates history points for detailed output and IP = 0 designates
history points for simplified output only IS is a switching flag between steadyunsteady
status in temperature calculation since this switching is automatically performed in the code
input of IP is usually unnecessary -FORMAT (6F 100 2I5)
F100 F100 F100 F100 F100 F100 I5 I5 I5 F50
A1 B2 A2 A5 A3 A4 IT IP IS A6
462 Relative power profile Here the input method for relative power profile is explained RH is the relative
power in the axial direction and designates the power ratio for A2 (linear heat rate which is
given by the history data) at each axial segment Therefore the number of RH data to be
input is NAX (number of axial segments) whose maximum is 40 When an identical
relative power is inputted at history points the input can be omitted using II (history point
option) FORMAT (8F80 I6) 8F 80 I6
(RH(I) I=1 NAX) II
JAEA-DataCode 2013-009
- 135 -
463 Input method of power history For input of power history the power-history-point number pairs of data (combination of
power history data and relative power profile) must be input
Example of input (1)
An example of input for a case with one axial segment where the power is increased
from 0 to 500 Wcm during a period of 10 hr is shown below Here the following values
are used fast neutron flux=25times1013 (ncm2sdots) when 500 Wcm is reached coolant
temperature= 51315 (K) coolant pressure= 34 (MPa) and coolant velocity= 30 (ms)
Example of input (1)
5050505050505050
2
00 51315 34 1 30
10 2
100 5000 25E13 1
5050505050505050
In the first line NHIST = 2 is shown the number of history points is 2
In the second line a hot stand-by state is set in the initial history data Input for the hot
stand-by state is not necessary since the following default values are set time (A1) 10minus5 (hr)
linear heat rate (A2) 10minus3 (Wcm) fast neutron flux (A5) 2times101 (ncm2sdots)
In the third line RH(1) = 10 is set since this case deals with a calculation of 1 axial
segment for the input of relative power profile The history point option is set as II = 2
which means that the same relative power profile is used for the two history points
The fourth line shows input of A1 = 10 (hr) A2 = 500 (Wcm) and A5 = 25times1013
(ncm2sdots) for the history data of the second history point so that the time step is automatically
divided and at each division point values of time-dependent variables are obtained by linear
interpolation Input of coolant temperature and coolant pressure is omitted this means that
the same values as those for the first history point are used that is A3=51314 and A4 = 34
are input For the output option IP = 1 is set in the second and third lines therefore detailed
output is performed both in the hot stand-by state and when 500 Wcm is reached
Example of input (2)
An example with 12 axial segments is shown in which base irradiation is first performed
at 200 Wcm up to 20GWdtUO2 The power is decreased thereafter and then increased to
250 Wcm After conditioning for 72 hr the power is increased to 500 Wcm maintained for
JAEA-DataCode 2013-009
- 136 -
24 hr and finally the power is decreased Here the power increase rate is 200 Wcmsdothr in
every period
The following values are set fast neutron flux=1014 (ncm2sdots) when 500 Wcm is
reached coolant temperature = 51315 (K) coolant pressure = 34 (MPa) and coolant
velocity is constant at 30 (ms) The relative power profile is given for base irradiation and
for ramp irradiation During the base irradiation output of calculation results is performed
at 5GWdt-UO2 10GWdt-UO2 15GWdt-UO2 and at 20GWdt-UO2 and during the ramp
irradiation the output of calculation is also performed at every 50 Wcm power increment
above 250 Wcm When the power is maintained at 500 Wcm the output of calculation is
obtained after 1 3 6 12 and 24 hr
Example of input (2) 5050505050505050 21 00 0001 20E09 51315 34 2 30 077 085 090 092 094 096 098 100 102 105 110 115 7 10 2000 40E13 1 50000 100000 150000 200000 2000 40E13 1 10 0001 20E09 -100 1 10 0001 20E09 -100
093 094 095 096 097 098 099 100 101 102 104 106 14
125 2500 50E13 -100 720 2500 50E13 -100 1 025 -100 05 075 10 125 5000 10E14 1 10 -100 30 60 120 240 5000 10E14 1 25 0001 20E09 -100 1 STOP 5050505050505050
The simplified output is obtained for the 21 history points shown above Among these
history points IP ge 1 is designated only at points where detailed output is required here IP =
2 is inputted and detailed output information is obtained at history points after this designation
The unit of burnup should be MWdt-UO2 therefore IBUNP = 0
The first line shows the number of history points NHIST = 21
The second line shows the history data of the hot stand-by state
JAEA-DataCode 2013-009
- 137 -
Data in the third and fourth lines show that the same relative power profile is used from the
first history point to the 7th history point
The fifth line shows the second history point data of A1 = 1(hr) A2 = 200(Wcm) and A5
= 4times1013 (ncm2sdots) Coolant temperature and pressure are the same as those in the hot
stand-by state
The 6-th to 9-th lines show input to extend burnup up to 20 GWdtUO2 at 200 (Wcm) and
simplified output is obtained at 5 GWdtUO2 and at 15 GWdtUO2 A2 (linear heat rate) and
A5 (fast neutron flux) are obtained by interpolation During this stage A2 = 200 (Wcm)
and A5 = 4times1013 (ncm2sdots) are used
The 10-th line shows setting of IT = minus100 This means that the power was decreased to
0001 (Wcm) within 1 hr from the burnup of 20 GWdtUO2 shown in line 8
The 11-th line shows that the relative power profile was changed after the power leveled
off at 0001 (Wcm) for 1 hr
The 12-th and 13th lines show that the relative power profile given in the 12-13th lines is
applied from the 14-th history point up to the last (26-th) history point Here since a power
of 0 is not allowed a value of around 10minus3 (Wcm) must be set
The 14-th line shows that the power was increased to 250 (Wcm) within 125 hr and the
15-th line shows that the power was maintained at 250 (Wcm) for 72 hr
The 15-th to 20-th lines show that the power was increased by 50 Wcm within 025 hr
(200 Wcmsdothr) after being maintained at 250 (Wcm) for 72 hr Namely elapsed time at the
previous history point where IT = minus100 was designated (shown in the 14-th line) is given by
A1 Since the linear heat rate is given by the linear interpolation setting of A2 = 300 350
400 and 450 in lines 17-20 gives the same results Similarly the fast neutron flux used here
gives the same results by setting A5 = 6times1013 7times1013 8times1013 and 9times1013
The 21-25rd lines show history data which were set to obtain simplified output when the
power is maintained at 500 (Wcm) and at 1 3 6 and 12 hr from the starting time The
detailed output is obtained 24 hr after the starting time
The 26-th line shows that the power was decreased within a 25hr period starting from 24
hr from the starting time Here since the coolant temperature and pressure were set as
constant input for them at the second and later history points was omitted Also since
linear heat rate and fast neutron flux are obtained by linear interpolation input error occurs if
no power is generated at the last history point (Both values should not be zero)
JAEA-DataCode 2013-009
- 138 -
47 Setting of cladding outer surface temperature
In FEMAXI it is possible to simulate transition boiling and investigate changes in the
stress strain deformation oxidation buckling pellet surface temperature and internal
pressure while omitting the calculation of the heat transfer to coolant by designating a history
of the cladding outer surface temperature using input data
The cladding outer surface temperature is designated using IS of the history data IS is
an option to designate conditions of gas flow and heat transfer calculation
IS=0 Stable calculation (fission gas released inside a fuel rod is instantaneously and
completely mixed with gap gas and plenum gas Cladding temperature is calculated
without considering heat capacity of the gas)
IS=1 Gas flow calculation (fission gas flows inside the fuel rod and is distributed and
mixed with gap gas and plenum gas However heat capacity of the gas is not
considered in the calculation of the cladding temperature)
IS=2 Unsteady calculation (fission gas flows inside the fuel rod and distributed and
mixed with gap gas and plenum gas Heat capacity of the gas is considered in the
calculation of the cladding temperature)
In FEMAXI IS=3 is newly included for the heat transfer calculation in which the cladding
outer surface temperature is assigned
IS=3 Heat transfer calculation by designating the cladding outer surface temperature
At the history point where IS=3 is designated axial distribution of the cladding outer
surface temperature is designated by input
For the historical points in which IS=3 is assigned the axial distribution of the cladding
outer surface temperature can be assigned by input
JAEA-DataCode 2013-009
- 139 -
Table 471 shows an example of inputs when the cladding outer surface temperature is
not assigned (ISlt3) and Table 472 shows an example when the cladding outer surface
temperature is assigned (IS=3) Here the data for the cladding outer surface temperature are
described after inputting the power profile in the axial direction
Table 471 Example of inputs without designation of cladding outer surface temperature
TSURUGA 1 NEW TYPE (BWR 8X8)
$INPUT IBUNP=1ICK1=0GR=10IPLT=1BETAX=0002IFEMRD=0
R1=1EPSRLZ=5D-3IPLOPT=-5DMAX=1GRWF=1SBU=1D4FCRFAC=1
IWTHE=181IPTHCN=5BUMIN=50000BUMAX=200000IURS=0
ICORRO=1EFCOEF=1INPCK=0
$END
10 5 2
0 1058 1230
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
3235 03 10 00 00 00
9
0001 53D13 55035 6894 0 1974
10 10 10 10 10 10 10
10 10 10 9
100 2500 53D13 0
02777778 2500 53D13 -100 1
00027778 2500 53D13 -100 1
00005556 2500 53D13 -100 1
00416667 2500 53D13 -100 1
00005556 2500 53D13 -100 1
00027778 2500 53D13 -100 1
02777778 2500 53D13 -100 1
STOP
JAEA-DataCode 2013-009
- 140 -
Table 472 Example of inputs with designation of cladding outer surface temperature
TSURUGA 1 NEW TYPE (BWR 8X8)
$INPUT IBUNP=1ICK1=0GR=10IPLT=1BETAX=0002IFEMRD=0
R1=1EPSRLZ=5D-3IPLOPT=-5DMAX=1GRWF=1SBU=1D4FCRFAC=1
IWTHE=181IPTHCN=5BUMIN=50000BUMAX=200000IURS=0
ICORRO=1EFCOEF=1INPCK=0
$END
10 5 2
0 1058 1230
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
0 0 00 103 104 003 095 366
3235 03 10 00 00 00
9
0001 53D13 55035 6894 0 1974
10 10 10 10 10 10 10 10
10 10 9
100 2500 53D13 0
02777778 2500 53D13 -100 1 3
553 553 553 553 553 553 553 553 553 553
00027778 2500 53D13 -100 1 3
603 603 603 603 603 603 603 603 603 603
00005556 2500 53D13 -100 1 3
923 923 923 923 923 923 923 923 923 923
00416667 2500 53D13 -100 1 3
923 923 923 923 923 923 923 923 923 923
00005556 2500 53D13 -100 1 3
603 603 603 603 603 603 603 603 603 603
00027778 2500 53D13 -100 1 3
553 553 553 553 553 553 553 553 553 553
02777778 2500 53D13 -100 1 3
553 553 553 553 553 553 553 553 553 553
STOP
Cladding surface temperature IS
JAEA-DataCode 2013-009
- 141 -
5 Models and Input manual of RODBURN-1
51 General feature of RODBURN input format
Input method of RODBURN is described below Here the input method will change in accordance with the designation of Card No2 ldquoKREG1rdquo so that the method will be explained in the two cases ie KREG1gt0 and KREG1=0 In the case KREG1gt0 users can make input data and parameters at usersrsquo will while in the other case KREG1=0 users can make a standard default set of input data and parameters in an easy manner The case KREG1gt0 will be explained in the input-data-format (1) and the other case KREG1=0 will be explained in the input-data-format (2)
52 Some comments on the RODBURN code (Sept1998)
The RODBURN code has two types of versions One is based on the ORIGEN (ORIGEN79(51)) the other is based on ORIGEN2(52) The ORIGEN79-basis version has been released to the NEA Data_Bank as RODBURN-1 in which resonance absorption calculation uses the RABBLE code to replace (update) the cross section data of U-238(n γ) and Pu-240(n γ) The cross section library of ORIGEN79 is those for the fuel body region though it cannot deal with the cross section changes induced by self-shielding effect of 238U in every part of fuel region This drawback is supplemented by RABBLE(53) with ENDF-BIV(52) data On the other hand ORIGEN-2 used in RODBURN-2 targets the fuel body region In ORIGEN-2 a library is implemented which can give the cross section changes induced by averaged changes of nuclides during burning ORIGEN2 treats the spectrum by one-group approximation for usersrsquo convenience so that it cannot bring in the resonance calculation results (RABBLE results) Therefore RODBURN-2 is suitable for an overall trend of fuel change during burning but it cannot give the power density profile in the radial direction of fuel pellet This is contradictory with the basic purpose of such fuel performance code as FEMAXI
The bottom line is that RODBURN-1 using ORIGEN79 is appropriate for a fuel performance code If the cross section changes with burning are to be taken into account every one step of burning calculation should call RABBLE to update the cross section values However dependence of the resonance integral on burnup is not so strong Thus RODBURN-1 takes a simplified method which uses RABBLE calculation only once at zero-burnup Fig51 summarizes the structure of calculation flow and relationship among the roles of component codes
JAEA-DataCode 2013-009
- 142 -
Fig51 Calculation flow of RODBURN-1
INPUT (Spatial meshing of rod assignment of elements and materials and power history)
1 Resonance Integral in each mesh Separate resonance Parameters by ENDB-IV (05eV~352keV)
2 RABBLE
Microscopic cross-section
Infinite diluting cross- section by WIMS-D library (352keV~0821MeV)
1E Spectrum
Revision of ORIGEN resonance library of U Pu and their isotopes
Calculates amount of fissile material in the axial segment of rod
Specifies three group spectrum constants (thermal fast resonance) ORIGEN rarr PWR amp BWR
Determines thermal neutron flux profile in the radial direction by the table of representative profiles in PWR and BWR (WIMS-D ) Halden reactor larr Robertsonrsquos formula Fast and resonance flux larr average values
Calculates power per unit flux at all meshes
Calculates flux at all meshes
Burnup calculation by ORIGEN
Axial profile of linear heat rate
Output File
∆t increment
JAEA-DataCode 2013-009
- 143 -
53 Explanations of RODBURN-1 models and methods
RODBURN has several types of default profile of power distribution RODBURN does not perform a so-called neutron transport calculation which is conducted by some other dedicated burning analysis codes such as PLUTON or MICROS The following section is an excerpt translated from the original report of RODBURN written by MrMUchida in Japanese [MUchida and HSaito RODBURN A Code for Calculating Power Distribution in Fuel Rods JAERI-M 93-108 (1993)] - - - - - - - - - - - - - - - - - - - - - - - - Beginning of excerpt - - - - - - - - - - - - - - - - - - - - - - - - - 22 Method of radial power profile in RODBURN (1) In case when neutron flux is given In accordance with the logics of the ORIGEN code neutron flux is based on the thermal neutron flux The fast neutron flux and epithermal flux are calculated in proportion to the thermal flux using spectrum parameters The thermal flux is a function of time and axial and radial locations inside the rod (rz t)t tφ φ= (2) Here input quantity is an averaged neutron flux over radius and its relative profile in the axial direction
2
0
1(z t) (r z t) 2
prat t pr dr rφ φ =
int (3)
where pr is the pellet radius
The three spectrum parameters THERM RES and FAST are used in accordance with ORIGEN
0THERM4
TT
π= (4)
where T is thermal neutron temperature (K) and T0=29316K RES = [resonance neutron flux per unit lethargy][thermal neutron flux] (5) FAST = [Fast neutron flux][thermal neutron flux] (6)
Here upper limit of the thermal neutron region is set 05 eV lower limit of fast region is set 1 MeV These three constants are included in RODBURN for each reactor type They are listed in Table 51 For PWR and BWR the recommended values(55) of ORIGEN are adopted as they are For a heavy water reactor only the value for the Halden reactor is
JAEA-DataCode 2013-009
- 144 -
specified and the three constants are derived from of the spectrum distribution determined in the Halden Project However they would be substantially applicable to other heavy water reactor In the axial direction of rod these three group spectrum distributions are treated in a variable separation from space distribution That is if thermal flux is twice larger at a certain axial elevation than at the other elevation the resonance and fast fluxes are assumed also twice However in the radial direction of rod different procedure is done depending on spectrum Average figures over radius are used for the fast and resonance fluxes as
(rz t) (z t)fast fastφ φ= (rz t) (z t)resonance resonanceφ φ= (7)
Radial distribution of thermal flux can be depressed toward the center region when a fuel pellet has high enrichment Consequently for the radial distribution of thermal flux several pre-calculated relative profiles depending on the reactor type and enrichment level are included in RODBURN and they are used by interpolation with respect to actual enrichment These relative profile figures are listed in Table 52 The profiles in the Halden reactor are listed in Table 53 In the initial stage of irradiation the enrichment is uniform in the radial direction However with burnup distribution of residual U-235 becomes non-uniform Moreover generation of Pu is much more non-uniform However in the code these non-uniformities are neglected and average concentrations of fissile materials at a certain axial elevation are used to interpolate the figures in the Table Here Pu-238 and Pu-241 is assumed as equivalent to U-235 The relative figures of thermal flux in Table 2 have been calculated by the WIMS-D code(54) The figure of a heavy water reactor has been derived on the basis of the following method recommended by the Halden Project
0(r) ( )therm CI rφ κ= (8)
where C is a normalization constant Io is a modified Vessel function r is radius (cm) and κis the reverse of diffusion distance (cm-1) given by
08 082 0190328( ) 054 ( )pdκ ερ ερminus= + (9)
where ε is enrichment () ρ is theoretical density ratio of pellet and pd is pellet
diameter (cm) The resonance absorption by U-238 has a strong self-shielding effect due to its high concentration so that the Pu generation is much deviated to the outer region of pellet
JAEA-DataCode 2013-009
- 145 -
Amount of Pu-240 is not so large even in MOX fuel nevertheless the resonance cross section (resonance reaction rate) is still larger As stated in the former section such distributions as those which are steeply deviated to the surface region cannot be dealt with by ORIGEN Therefore the RODBURN code has implemented the resonance calculation code RABBLE as one of the components and let RABBLE to calculate the resonance integral of the above two elements for each of the radially-divided sections in the first step of the whole burning process calculation In the ORIGEN calculation following this first calculation for the two elements U-238 and Pu-240 only the calculated results by RABBLE are used instead of the ORIGEN library data (2) In case when linear power history is given There are some cases of fuel experiments in which only history of the average power of rod is reported In this case also it is necessary to calculate the power density profile and changes of fissile and fission-product elements composition To cope with such a case in a simplified and convenient manner this ldquolinear power history is givenrdquo option has been implemented In this option contrary to the ordinary calculation steps the code calculates the neutron flux which corresponds to the input average power history However in general a reported power history is often a result of calculating Pu buildup on some appropriate assumption so that it is preferable to execute repeated calculations using the condition of section (1) ie ldquowhen neutron flux is givenrdquo under the assumption of history of an absolute value of neutron flux to confirm the reported average power history 1) Expression of neutron flux profile Since RODBURN does not perform a concurrent process of reactor physics calculation and burning analysis calculation it is necessary to assume the neutron flux profile in a reasonable way The fast and resonance fluxes are similarly to section (1) assumed uniform in the radial direction The thermal flux profile is determined by referring to the Table 52 in accordance with the fissile materials concentrations The axial profile is assumed to have an identical shape similarly to section (1) The simplest shape in the axial direction is a cosine profile This profile is modified in order to express a profile which is different to some extent
cos
( )cos
m
b t
m
b t
z zAL
z tz z
L
πδ δ
φαπ
δ δ
minus + + =
minus + +
(10)
( ) 2m b tz L δ δ= + + (11) where A is a normalizing constant L is an axial length of fuel stack z is a distance from
JAEA-DataCode 2013-009
- 146 -
bottom of pellet stack bδ and tδ are ldquoextrapolating distancerdquo from the top end and bottom end respectively α is a constant to express ldquoa slightly flattened profile in comparison with the cosine profilerdquo and it can be varied within the range of 0 1αle lt When 0α = the denominator of Eq(10) is 10 so that the profile becomes the cosine profile itself With increasing α the profile is flattened The two bδ and tδ ldquoextrapolating distancesrdquo aim to express a special type of irradiation condition in test reactor rather than the ldquoextrapolating distancerdquo usually used in reactor physics In irradiation experiments of fuel it often occurs that a test rod shorter than the height of reactor core is set at the axial elevation deviated from the mid-height position of the reactor core In such a case the neutron flux profile can be expressed by designating the two extrapolating distances independently It is also possible to calculate the profile shape in advance and to input the shape as a series of numerical values In both the cases the relative profile of neutron flux in the axial direction can be changed a few times during the irradiation time 2) Calculation of the absolute neutron flux At the beginning of each time step concentration of every element is given at all the (r z) locations The cross section is fixed Also the neutron relative profile is given Assuming that this relative profile is expressed by a normalizing distribution function F(r z) total heat generation corresponding to the neutron flux averaged over entire fuel rod can be obtained by
0 0 ( )f fQ E F r z dvφ σ= int (12)
where fσ is fission cross section and fE is energy per one fission Assuming that the total
heat generation corresponding to the input average linear heat rate is Q an actual average neutron flux is simply
00
φ φ=
(13)
Neutron flux at each position is determined by this equation using F(r z) However in fact these calculations are performed by taking into account of every element fast neutron and thermal neutron Now that the local neutron flux is obtained ORIGEN calculates the changes of amount of every element during the time step so that ORIGEN is called again after the calculation of Eq(12) Here it is to be noted that during one time step in the input data a constant heat generation rate is assumed In the ORIGEN calculation amount of elements changes during one time step and in accordance with these changes an accumulated heat generation ie burn-up is calculated Therefore if time step increment is too large some discrepancy is capable of
JAEA-DataCode 2013-009
- 147 -
being generated among the input data burn-up and element concentrations To avoid this RODBURN re-divides the input time step into a number of small periods to prevent a too long time step
Table 51 Three group-constants of spectrum
Reactor type THERM RES FAST
PWR 0701 0304 2010
BWR 0676 0307 1514
HWR 0450 0100 1500
PWR (MOX) 0592 0366 2390
BWR (MOX) 0632 0355 1694
Table 52 Thermal neutron flux profile in the radial direction
In the Halden water reactor
Radius (mm)
Thermal neutron flux profile (Enrichment dependent) 1 3 5 7
201 1000 1000 1000 1000 284 1008 1025 1045 1068 347 1014 1043 1077 1117 401 1020 1060 1109 1165 449 1026 1078 1141 1216 491 1032 1096 1174 1267 531 1038 1114 1207 1319 567 1043 1132 1241 1372 602 1049 1150 1276 1428 634 1055 1168 1310 1483
JAEA-DataCode 2013-009
- 148 -
Tabl
e 5
3 T
herm
al n
eutro
n flu
x pr
ofile
s de
pend
ing
on e
nric
hmen
t R
adiu
s (m
m)
PW
R (U
rani
um)
PW
R (M
OX)
1
3
5
7
0
25
378
7
31
1
083
127
0
985
09
64
09
44
09
23
09
96
09
01
07
98
07
03
183
0
987
0
968
0
950
0
932
0
996
0
911
0
819
0
731
2
25
09
89
09
74
09
59
09
44
09
97
09
26
08
47
07
74
259
0
992
0
981
0
970
0
958
0
998
0
945
0
886
0
826
2
90
09
95
09
89
09
82
09
76
09
98
09
67
09
30
08
90
318
0
999
0
998
0
997
0
996
1
000
0
993
0
982
0
966
3
43
100
4 1
009
1
014
1
019
1
001
1
024
1
045
1
059
3
67
100
9 1
021
1
034
1
046
1
003
1
060
1
120
1
175
3
89
101
6 1
037
1
058
1
079
1
005
1
104
1
216
1
325
4
10
102
5 1
059
1
093
1
127
1
008
1
168
1
355
1
551
Rad
ius
(mm
)
B
WR
(Ura
nium
)
BWR
(MO
X)
1
3
5
7
025
3
78
731
10
83
1
90
09
90
09
77
09
64
09
51
09
93
08
44
06
98
05
70
268
0
992
0
980
0
968
0
957
0
994
0
861
0
728
0
609
3
29
09
93
09
83
09
74
09
64
09
95
08
85
07
71
06
68
379
0
995
0
988
0
980
0
973
0
996
0
914
0
825
0
740
4
24
09
97
09
93
09
88
09
84
09
98
09
49
08
90
08
29
465
0
999
0
998
0
998
0
997
1
000
0
989
0
968
0
937
5
02
10
02
10
05
10
09
10
12
10
02
10
37
10
61
10
72
537
1
006
1
014
1
021
1
029
1
004
1
094
1
178
1
246
5
69
10
10
10
24
10
37
10
51
10
08
11
64
13
28
14
80
600
1
016
1
038
1
060
1
082
1
012
1
265
1
553
1
847
- -
- - -
- - -
- - -
- - -
- - -
- - -
- - -
- -
End
of e
xcer
pt
- - -
- - -
- - -
- - -
- - -
- - -
- - -
- - -
- - -
JAEA-DataCode 2013-009
- 149 -
54 Explanation of neutron flux control by ldquoALPH(K) EXTL(K) EXTT(K) K=1 NDISTrdquo Option for IDIST
IDIST allows an option to give the shape of axial profile of thermal neutron It allows to
select the shape of either (deformed) cosine curve or input numerical figure When IDIST=0
input of (ALPH(K) EXTL(K) EXTT(K) K=1 NDIST) is necessary This line is input
NDSIT times (=total number of profile patterns)
ALPH(I) flattening constant of the I-th pattern where 0≦ALPH(I)lt1
EXTL(I) Lower ldquoextrapolating distancerdquo (cm)
EXTT(I) Upper ldquoextrapolating distancerdquo (cm)
These are the constants used in the following equation to modify the cosine profile If
they are all set 0 a simple cosine profile is obtained Fig52 below shows as an example with A=10 L=10 bδ =05 tδ =05 and Zm=10 some profile shape patterns in which α is
parametrically changed When αgt0 a deformed cosine curve is given
Fig52 Example of profile shape with A=10 L=10 bδ =05 tδ =05 Zm=10 and α
which is parametrically changed
0
02
04
06
08
1
12
0 05 1 15 2 25
φ(z)
z
0012502503750506250750875
L (fuel active length)
Z=Zm
( ) cos cosm m
b t b t
z z z zz t AL L
ϕ π απδ δ δ δ
minus minus = + + + +
EXTT (δt)
EXTL (δb)
α
coscos)(
++
minus
++
minus=
tb
m
tb
m
Lzz
LzzAtz
δδαπ
δδπφ
JAEA-DataCode 2013-009
- 150 -
55 Some important input name-list parameters of FEMAXI-7 for usage of RODBURN-1
Name-list
input parameter
Contents Default value
IFLX
Number of power history points to designate the radial power profile If the numerical data are not given IFLX should be one of 0 -1 o -2 which corresponds to the following options
= 0 Robertson model -1PLUTON results -2 RODBURN results When IFLX=-1 or -2 corresponding results files should exist in the WrkRBOUT
0
FACHE When IFLXlt0 amount of He gas given by RODBURN calculation is multiplied by FACHE 10
IRH
Interpolation option of axial power profile = 0 the profile at omitted input points is the same as that in the previous
stage = 1 linear interpolation in terms of burnup is performed for omitted input
points
0
INPRD
Options for the fetching method of RODBURN results to FEMAXI-6 (Treatment of fast-neutron flux is designated by IFSNT)
INPRD=0 By interpolating the results of RODBURN (the radial and axial
profiles of power fast-neutron flux and He generation) with respect to space and burnup the data are arranged to correspond to the segments in the axial direction of FEMAXI
INPRD=1 An identical number of segments in the axial direction is assumed
for FEMAXI and RODBURN The results from RODBURN (the radial and axial profiles of power fast-neutron flux and He generation) are used as data for the corresponding axial segments No spatial interpolation is performed Interpolation of burnup is performed
INPRD=2 The number of segments in the axial direction can be different for
FEMAXI and RODBURN (interpolation processing is performed) With respect to the profiles of power and He generation in the radial direction the result of RODBURN is retrieved For the power profile in the axial direction the input to FEMAXI is used
1
IROD
When IRODgt0 an original input file ldquorodinrdquo for RODBURN is generated in the Wrk directory and FEMAXI calculation is not executed Users can modify the contents of this file and rename it to be used in RODBURN calculation eg ldquorodinrdquo to ldquoABCrddatrdquo
IROD=1PWR =2BWR =3Halden BWR =4PWR(MOX) =5 BWR(MOX)
0
JAEA-DataCode 2013-009
- 151 -
56 RODBURN Input data format (1) (When KREGI gt0 value is given in line No2)
Line No Variables FORMAT Content
1 TITLE 18A4 Title of calculation
2
MODEL
10I6
Reactor type option 1=PWR 2=BWR
3=Halden WR 4=PWR(MOX) 5=BWR(MOX)
MESHZ Number of axial zones ( le 40)
KREG1
Number of radial regions ( le 39 including coolant region
for resonance calculation) In the case of ldquoKREG1=0rdquo
follow the input-data format (2)
MESHR
Number of pellet regions in the radial regions ( le 36)
(Each axial zone can have different materials such as
enriched U natural U etc but each axial zone has to
have the same number of regions)
IOPT
Option to designate the irradiation history
=0 average thermal neutron flux is input
=1 average linear heat rate (Wcm) is input
IDIST
Option to designate axial profile of either thermal
neutron flux or linear heat rate
=0 (deformed ) cosine profile is input
=1 Numerical values are input
(Note even if IOPT=1 IDIST and related array data
should be given by either the line 15 or 16)
MODEL2 [can be omitted if reactor type is not changed]
Option to designate the change of reactor type in the
course of irradiation
Reactor type 1=PWR 2=BWR 3=Halden WR
4=PWR(MOX) 5=BWR(MOX)
Here MODEL2=MODEL is possible
KREG2 [can be omitted if reactor type is not changed]
Number of radial regions ( le 39 including coolant
region for resonance calculation) in MODEL2
However if MODEL2 is not designated or if
resonance calculation is not done in MODEL2 KREG2
is not designated
IFLPW IFLPW=0 axial profile of thermal neutron flux is input
IFLPW=1 axial profile of linear heat rate is input
ISTOP ISTOP=0 Regular calculation
ISTOP=1 Input checking calculation
JAEA-DataCode 2013-009
- 152 -
RODBURN Input data format (1_continued) (When KREGIgt0 value is given in line No2)
Line No Variables FORMAT Content
3 ZMESH(I)
I=1 MESHZ 9F84
Upper end coordinate value of each axial zone of active
length (cm)
4
RMIN
RMAX2(I)
I=1 KREG1
F80 8F80
( 8X 8F80)
RMIN fuel pellet inner radius (cm)
RMAX2(I) outer radius of each region (cm)
(ie center hole is not included in the ldquoregionsrdquo)
5 TEMP(I)
I=1 KREG1
8X 8F80
( 8X 8F80)
Temperature at each region (K)
(Rough values independent of time and axial zone)
6 NMIX I6 Total number of ldquomixturerdquo with different composition
7
(NUCLX(I)
CONCEX(I)
I=17)
7(I3 F73)
This line is repeated NMIX times consecutively
Each line corresponds to one mixture and specifies
maximum 7 nuclides
NUCLX(I) nuclides number below
CONCEX(I) concentration (gcm3)
Nuclides number
1 = 238U 2 = 240Pu 3 = H 4 = D
5 = 16O 6 = He 7 = Zr-2 8 = Zr-4
9 = 235U 10 = 239Pu 11 = 241Pu 12 = 242Pu
8
MIX(IJ)
I=1 KREG1
J=1 MESHZ)
30I2
This line is repeated MESHZ times consecutively
Each line corresponds to each axial zone In each line
specify what ldquomixturerdquo exists in each radial region from
inner region to outer region (The order to specify the
mixture in the line 7 is ldquomixture numberrdquo)
Only if KREG2ne0 designate the lines 9 to 13 Otherwise skip to the line 14
9
RMIN
RMAX3(I)
I=1 KREG2
F80 8F80
( 8X 8F80)
Radius of each region after reactor type change
RMIN pellet inner radius (cm)
RMAX3(I) outer radius of each region (cm)
(Center hole is not included in the ldquoregionsrdquo
Here pellet regions up to MESHR should be given
the same values as RMAX2(I) )
10 TEMP2(I)
I=1 KREG2
8X 8F80
( 8X 8F80)
Temperature at each region after reactor type change(K)
(Rough values independent of time and axial zone)
11 NMIX I6 Total number of ldquomixturerdquo with different composition
after reactor type change
JAEA-DataCode 2013-009
- 153 -
RODBURN Input data format (1_continued) (When KREGIgt0 value is given in line No2)
Line No Variables FORMAT Content
12
(NUCLX(I)
CONCEX(I)
I=1 7)
7(I3 F73)
This line is repeated NMIX times consecutively
Each line corresponds to one mixture and specifies
maximum 7 nuclides after reactor type change
NUCLX(I) nuclides number below
CONCEX(I) concentration (gcm3)
Nuclides number
1 = 238U 2 = 240Pu 3 = H 4 = D
5 = 16O 6 = He 7 = Zr-2 8 = Zr-4
9 = 235U 10 = 239Pu 11 = 241Pu 12 = 242Pu
Here number and concentrations of nuclides in pellet
should be the same as those specified in the line 7
13
(MIX2(I J)
I=1 KREG2
J=1 MESHZ)
30I2
This line is repeated MESHZ times consecutively
Each line corresponds to each axial zone In each line
specify what ldquomixturerdquo exists in each radial region from
inner region to outer region after reactor type change
(The order to specify the mixture in the line 12 is
ldquomixture numberrdquo However regions of pellet should
have the same data as those specified in the line 8)
14 NDIST I6
Number of patterns of axial profile of either neutron
flux (IFLPW=0) or linear heat rate (IFLPW=1) The
patterns can be specified at each time step
15
(ALPH(K)
EXTL(K)
EXTT(K)
K=1 NDIST)
3F84
(Not necessary when IDIST=1)
This line is input NDIST times consecutively
ALPH(I) Constant of averaging of the I-th pattern
where 0 le ALPH(I) lt 1
EXTL(I) Lower region extrapolation distance (cm)
EXTT(I) Upper region extrapolation distance (cm) (Theses constants modify the cosine profile If all the
values are set equal to 0 a normal cosine profile is given as input) See the explanation in section 54
16
(FLUXZ(IK)
I=1 MESHZ
K=1 NDIST)
12F82
(Not necessary when IDIST=0)
This line is input NDIST times consecutively
IFLPW=0 axial profile of thermal neutron flux is input
IFLPW=1 axial profile of linear heat rate is input
JAEA-DataCode 2013-009
- 154 -
RODBURN Input data format (1_continued) (When KREGIgt0 value is given in line No2)
17 ISTP DTIME I6 E125
ISTP Number of time steps ( le 200) DTIME The longest period of time step (day)
The ldquonumber of time stepsrdquo specified here is the times of specifying the approximate pattern of output power history Total period of irradiation can be one single time step The code automatically divides each input step period into the period which is not longer than DTIME
It is better to specify the length of DTIME to be less than the period during which irradiation is less than 1times1020ncm2 within the 200 time steps
18
(TIMX(I)
KDIS(I)
PLHR(I 1)
PLHR(I 2)
ICHG
I=1ISTP)
E125 I6
2E125 I6
(Input ISTP times consecutively) TIMX(I) end of I-th step (day) KDIS(I) Number of the I-th step pattern of either thermal neutron flux profile or linear heat rate profile (variable ldquokrdquo in the lines 15 and 16)
PLHR(I 1) PLHR(I 2) Average powers at the beginning and end of the I-th step respectively
IOPT = 0 average thermal neutron flux (ncm2s) IOPT = 1 average linear heat rate (Wcm) ICHG when MODEL2 gt 0 ICHG=1 should be
designated at the time TIMX(I) when reactor type changes In other cases ICHG is not designated
19 NPRINT I6 Total number of time steps at which the results are
printed out Besides these the final result is printed out additionally
20 TIMPRN(I) I=1 NPRINT
9F82 Tine of print-out of numerical results (day) From the
first step after TIMPRN(I) results are printed out sequentially
21 IDIMPR(I) I=1 NPRINT
9I8
Corresponding to the line 20 specify what type of output is printed out IDIMPR=1 only 1-dimensional data is output (Eg axial zone-wise averaged burnup are printed
out for all the axial zones) =2 1-dimensional data and (r z) distributions of
power generation variables Limited to the axial zones which are specified by the line 22
=3 In addition to the above 2-dimensional nuclides contents are output (Limited to the axial zones which are specified by the line 22)
22 IZD2(I) I=1 12
12I6 The axial zone numbers for the 2-dimensional output are specified sequentially as needed
23 STOP A4 To define the end of the input data ldquoSTOPrdquo should be input from the 1-st column to the 4-th column
JAEA-DataCode 2013-009
- 155 -
57 RODBURN Input data format (2) (when KREGI=0 in line No2)
Line No Variables FORMAT Content
1 TITLE 18A4 Title of calculation
2
MODEL
10I6
Reactor type option 1=PWR 2=BWR
3=Halden WR 4=PWR(MOX) 5=BWR(MOX)
MESHZ Number of axial zones ( le 40)
KREG1 Specify ldquoKREG1=0rdquo This gives KREG1=MESHR+3
MESHR
Number of pellet regions in the radial regions ( le 36)
Each axial zone can have different materials such as
enriched U natural U etc but each axial zone has to
have the same number of regions
IOPT
Option to designate the irradiation history
=0 average thermal neutron flux is input
=1 average linear heat rate (Wcm) is input
IDIST
Option to designate axial neutron flux profile (or
power profile)
=0 (deformed ) cosine profile is input
=1 Numerical values are input
(Note even if IOPT=1 IDIST and related array data
should be given by either the line 10 or 11)
MODEL2 [can be omitted if reactor type is not changed]
Option to designate the change of reactor type in the
course of irradiation
Reactor type 1=PWR 2=BWR 3=Halden WR
4=PWR(MOX) 5=BWR(MOX)
Here MODEL2=MODEL is possible
KREG2 [can be omitted if reactor type is not changed]
Number of radial regions ( le 39 including coolant
region for resonance calculation) in MODEL2
However if MODEL2 is not designated or if
resonance calculation is not done in MODEL2 KREG2
is not designated
IFLPW
IFLPW=0 axial profile of thermal neutron flux is input
(eg Halden Reactor)
IFLPW=1 axial profile of linear heat rate is input
ISTOP ISTOP=0 Regular calculation
ISTOP=1 Input checking calculation
JAEA-DataCode 2013-009
- 156 -
RODBURN Input data format (2-continued) (when KREGI=0 in line No2)
Line No Variables FORMAT Content
3
IAUTO
7I6
IAUTO=0 Input the nuclides number and concentrations
of mixtures in each of the pellet cladding and coolant
regions
IAUTO=1 default values are set (notes 1 2 and 8)
IPTCH1
Option before reactor type change
IPTCH1=0 input the outer diameter of coolant boundary
IPTCH1=1 input fuel rod pitch
IZR1
(note 1)
Cladding material option before reactor type change
(IZR1=2 Zry-2 IZR1=4 Zry-4)
IHD1
(note 2)
Coolant option before reactor type change
(IHD1=0 H2O IHD1=1 D2O)
IPTCH2
(note 6)
Option after reactor type change
IPTCH2=0 input the outer diameter of coolant
boundary
IPTCH2=1 input fuel rod pitch
IZR2 (note 1) Cladding material option after reactor type change
(IZR2=2 Zry-2 IZR2=4 Zry-4)
IHD2 (note 2) Coolant option after reactor type change
(IHD2=0 H2O IHD2=1 D2O)
4
ZLENG
(note 3)
7F80
Active length of fuel rod (cm)
PDIN Pellet inner diameter (cm) PDIA
(note 4) Pellet outer diameter (cm) CDOUT1
(note 5) Cladding outer diameter before reactor type change (cm)
PITCH1 (note 6)
Coolant boundary diameter before reactor type change
(IPTCH1=0) or fuel rod pitch (IPTCH1=1) (cm) CDOUT2
(note 5) Cladding outer diameter after reactor type change (cm)
PITCH2 (note 6)
Coolant boundary diameter after reactor type change
(IPTCH2=0) or fuel rod pitch (IPTCH2=1) (cm)
JAEA-DataCode 2013-009
- 157 -
RODBURN Input data format (2-continued) (when KREGI=0 in line No2)
Line No Variables FORMAT Content
5
(note 7)
TP1
8F80
Pellet center temperature before reactor type change (K)
TS1 Pellet surface temperature before reactor type change(K)
TC1 Cladding temperature before reactor type change (K)
TW1 Coolant temperature before reactor type change (K)
TP2 Pellet center temperature after reactor type change (K)
TS2 Pellet surface temperature after reactor type change (K)
TC2 Cladding temperature after reactor type change (K)
TW2 Coolant temperature after reactor type change (K)
When IAUTO=0 specify the lines 6 and 7 When IAUTO=1 specify the line 8
6
(NUCLX(I)
CONCEX(I)
I=17)
7(I3 F73)
This line is repeated three times consecutively
Each line corresponds to one mixture and specifies
max7 nuclides before reactor type change
NUCLX(I) nuclides number below
CONCEX(I) concentration (gcm3)
Nuclides number
1 = 238U 2 = 240Pu 3 = H 4 = D
5 = 16O 6 = He 7 = Zr-2 8 = Zr-4
9 = 235U 10 = 239Pu 11 = 241Pu 12 = 242Pu
Only when KREG2gt0 specify the line 7
7
(NUCLX(I)
CONCEX(I)
I=1 7)
7(I3 F73)
This line is repeated three times consecutively
Each line corresponds to one mixture and specifies
max7 nuclides after reactor type change
NUCLX(I) nuclides number below
CONCEX(I) concentration (gcm3)
Nuclides number
1 = 238U 2 = 240Pu 3 = H 4 = D
5 = 16O 6 = He 7 = Zr-2 8 = Zr-4
9 = 235U 10 = 239Pu 11 = 241Pu 12 = 242Pu
Here number and concentrations of nuclides in pellet
should be the same as those specified in the line 6
JAEA-DataCode 2013-009
- 158 -
RODBURN Input data format (2-continued) (when KREGI=0 in line No2)
Line No Variables FORMAT Content
When IAUTO=1 specify the line 8
8
(note 8)
FDEN 6F80
Pellet theoretical density ratio (-)
FU235 U-235enrichment (-)
FPUO2
[If fuel contains no Pu this line can be omitted]
PuO2 weight ratio
+ 22
2
PuOUOPuO (-)
FPU240 Pu-240 weight ratio
minus totPuPu240
(-)
FPU241 Pu-241 weight ratio
minus totPuPu241
(-)
FPU242 Pu-242 weight ratio
minus totPuPu242
(-)
9 NDIST I6
Total number of patterns of the axial profiles of either
neutron flux (IFLPW=0) or linear heat rate
(IFLPW=1) This can be specifies at each time step
10
(ALPH(K)
EXTL(K)
EXTT(K)
K=1 NDIST)
3F84
(Not necessary when IDIST=1) This line is input NDIST times consecutively ALPH(I) Constant of averaging of the I-th pattern where 0 le ALPH(I) lt 1 EXTL(I) Lower region extrapolation distance (cm) EXTT(I) Upper region extrapolation distance (cm) (This modifies the cosine profile If all the values are set equal to 0 a normal cosine profile is given as input)
See the explanation in section 54
11 (FLUXZ (I K)
I=1 MESHZ) 12F82
(Not necessary when IDIST=0)
This line is input NDIST times consecutively
IFLPW=0 axial profile of thermal neutron flux is input
IFLPW=1 axial profile of linear heat rate is input
12 ISTP DTIME I6 E125
ISTP Number of time steps ( le 200)
DTIME The longest period of time step (day) The ldquonumber of time stepsrdquo specified here is the times of specifying the approximate pattern of output power history Total period of irradiation can be one single time step The code automatically divides each input step into sub-steps which are not longer than DTIME It is better to specify the length of DTIME to be less than the period during which irradiation is less than 1 times
1020ncm2 within the 200 time steps
JAEA-DataCode 2013-009
- 159 -
RODBURN Input data format (2-continued) (when KREGI=0 in line No2)
Line No Variables FORMAT Content
13
(TIMX(I)
KDIS(I)
PLHR(I 1)
PLHR(I 2)
ICHG
I=1 ISTP)
E125 I6
2E125 I6
This line is input ISTP times consecutively
TIMX(I) end of I-th step (day)
KDIS(I) Number of the I-th step pattern of either
thermal neutron flux profile or linear heat rate profile
(variable ldquoKrdquo in the lines 10 and 11)
PLHR(I 1) PLHR(I 2) Average powers at the
beginning and end of the I-th step respectively
IOPT = 0 average thermal neutron flux (ncm2s)
IOPT = 1 average linear heat rate (Wcm)
ICHG when MODEL2 ne 0 ICHG=1 should be
designated at the time TIMX(I) when reactor type
changes In other cases ICHG is not designated
14 NPRINT I6
Total number of time steps at which the results are
printed out Besides these the final result is printed out
additionally
15 TIMPRN(I)
I=1 NPRINT 9F82
Tine of print-out of numerical results (day)
(From the first step after TIMPRN(I) results are printed
out sequentially)
16 IDIMPR(I)
I=1 NPRINT 9I8
Corresponding to the line 15 specify what type of
output is printed out IDIMPR=1 only 1-dimensional data is output (Eg axial zone-wise averaged burnup are printed
out for all the axial zones) =2 1-dimensional data and (r z) distributions
of power generation variables Limited to the axial zones which are specified by the line 17
=3 In addition to the above 2-dimensional
nuclides contents are output (Limited to the axial
zones which are specified by the line 15)
17 IZD2(I)
I=1 12 12I6
The axial zone numbers for the 2-dimensional output are
specified sequentially as needed
18 STOP A4 To define the end of the input data ldquoSTOPrdquo should be
input from the 1-st column to the 4-th column
JAEA-DataCode 2013-009
- 160 -
(note 1) Densities of Zry-2 and Zry-4 are assumed as 655 (gcm3)
(note 2) In light water (H2O) density of H= 0079(gcm3) density of O=0631(gcm3)
In heavy water (D2O) density of D= 01807(gcm3) density of O=07226(gcm3)
(note 3) Length of each axial zone is given by equally dividing the total active length of rod by
ldquoMESHZrdquo
(note 4) Pellet is divided into equal-volume ring elements The number of the ring elements is
specified by ldquoMESHRrdquo
(note 5) It is assumed that a cladding has one region
(note 6) It is assumed that coolant has two regions When rod-to-rod pitch is specified coolant
outer boundary radius r is given by PITCHrπ
=
(note 7)
Approximating the temperature distribution inside a pellet by a quadrature function gives
the temperature of i-th region from the center as
( )2
12lowast
minuslowastminusminus=
MESHRITTTT sPPi
Where TP pellet center temperature and Ts pellet surface temperature
(note 8)
Calculation method of element compositions (gcc) of fuel pellet are described below
(1) Calculation of theoretical density of MOX fuel Assuming the theoretical density of MOX fuel as ρ weight ratio of UO2 as
2UOF
weight ratio of PuO2 as2PuOF volume ratio of UO2 as
2UOV and volume ratio of PuO2
as 2PuOV the followings hold
1
1
22
22
222
222
=+
=+
sdot=sdot
sdot=sdot
PuOUO
PuOUO
UOUOUO
PuOPuOPuO
FF
VV
FV
FV
ρρ
ρρ
where2UOρ =1096(gcc)
2PuOρ =1146(gcc) Eliminating 2UOV
2PuOV and 2UOF
from the above Eqs and solution with respect to ρ gives
( )2222
22
PuOUOPuOPuO
PuOUO
F ρρρρρ
ρminus+
sdot=
(2) Calculation of each weight ratio
Each weight ratio is defined as follows 2
2 2
2
2 2
2
2
UO
PuO
UOFUO PuO
PuOFUO PuO
=+
=+
235
235 235 238
238
238 235 238
U
U
UFU U
UFU U
=+
=+
JAEA-DataCode 2013-009
- 161 -
(note 8)
PuPuPuPuPuF
PuPuPuPuPuF
PuPuPuPuPuF
PuPuPuPuPuF
Pu
Pu
Pu
Pu
242241240239
242
242
242241240239
241
241
242241240239
240
240
242241240239
239
239
+++=
+++=
+++=
+++=
2
2
PuOPuF
UOUF
Pu
U
=
=
Here values of 2PuOF FU235 FPu240 FPu241 and FPu242 are given by input
As a result FUO2 FU238 and FPu239 are determined by the above equations
Also for FU and FPu th next equations hold
235 238
235 238
239 240 241 242
239 240 241 242
235 238235 238 32
239 240 241 242239 240 241 242 32
U UU
U U
Pu Pu Pu PuPu
Pu Pu Pu Pu
F FFF F
F F F FFF F F F
sdot + sdot=
sdot + sdot +sdot + sdot + sdot + sdot
=sdot + sdot + sdot + sdot +
Therefore each elemental composition (concentration) can be determined by the
following equations
( ) ( )
235 235
238 238
239 239
240 240
241 241
242 242
2
2
2
2
2
2
2 21 1
U U U UO D
U U U UO D
Pu Pu Pu PuO D
Pu Pu Pu PuO D
Pu Pu Pu PuO D
Pu Pu Pu PuO D
o U UO Pu PuO D
F F F F
F F F F
F F F F
F F F F
F F F F
F F F F
F F F F F
ρ ρ
ρ ρ
ρ ρ
ρ ρ
ρ ρ
ρ ρ
ρ ρ
= sdot sdot sdot sdot
= sdot sdot sdot sdot
= sdot sdot sdot sdot
= sdot sdot sdot sdot
= sdot sdot sdot sdot
= sdot sdot sdot sdot
= minus + minus sdot sdot
where FD is the pellet theoretical density ratio (-)
References 5 (51) Bell MJ ldquoORIGEN ndash The ORNL Isotope Generation and Depletion Coderdquo
ORNL-4628 (1973) (52) Croff AG ldquoORIGEN2- A Revised and Updated Version of the Oal Ridge Isotope
Generation and Depletion Coderdquo ORNL-5621 (1980)
JAEA-DataCode 2013-009
- 162 -
(53) Kier PH and Robba AA ldquoRABBLE A Program for Computation of Resonance Absorption in Multiregion Reactor Cellsrdquo ANL-7326 (1967)
(54) WIMS-D IAEA Nuclear Data Services httpwww-ndsiaeaorg (55) Croff AG et al ldquoRevised uranium-plutonium cycle PWR and BWR models for the
ORIGEN computer coderdquo ORNLTM-6051 (1978)
(56) ENDF-BIV IAEA Nuclear Data services httpwww-ndsiaeaorg
JAEA-DataCode 2013-009
- 163 -
6 Input Manual of Plotting Control Program EXPLOT
61 Input parameters for EXPLOT Line No SYMBOL (FORMAT) 1 Comments 2 ISET () Total number of figures Input ISET-sets consisting of the following lines IRNUM ITOPT NOLINE () Function setting
3
IRNUM number of lines drawn in one figure (max 5 lines)
ITOPT designation of graph type ITOPT = 0 X axis represents time burnup or linear heat rate ITOPT = 1 X axis represents coordinates in the radial or axial direction (relative value
is allowed) ITOPT = 2 Construct a diagram for comparison of calculated values with measured
values (in this case maximum value of IRNUM becomes 4 since one line is used for the measured values)
ITOPT=3 X axis represents either radius or axial coordinate Designation method of ITIM in line 7 is different from the case of ITOPT=1
NOLINE Grid line (broken line) option = 0 Grid line is not plotted = 1 Grid line is plotted =2 Grid line is plotted When once or more in ISET-sets lines NOLINE=2 is designated the corresponding CSV file is output with sets of the radial and axial coordinates time and physical quantity = -1 When once or more in ISET-sets lines NOLINE= -1 is designated the PS file is not generated = -2 When once or more in ISET-sets lines NOLINE= -1 is designated the PS file is not
generated but CSV file is output with sets of the radial and axial coordinates time and physical quantity
Accordingly when once or more in ISET-sets lines NOLINElt0 is designated the PS file is not generated
JAEA-DataCode 2013-009
- 164 -
IXOPT IXOPT2 IYOPT2 IYNUM (IYOPT(I) I=1 IYNUM) () Axis setting
4
IXOPT setting of the contents of X axis (set when ITOPT = 0 or 2) = 1 time = 2 coordinates in the radial direction (minus) (set when ITOPT = 1) = 3 coordinates in the axial direction (minus) (set when ITOPT = 1) = 4 burnup (at the objective segment set by IXOPT2) = 5 linear heat rate (at the objective segmentWcm) = 6 burnup (average on all axial segments set by IXOPT2) =7 linear heat rate (average on all axial segmentsWcm) =8 elapsed time from the point designated by ITIM(1) in the input line 7 =9 energy density (calg-fuel) IXOPT2 setting of units for time and burnup Setting of units when X axis represents time (IXOPT = 1) (Dummy when IXOPTgt1 ) IXOPT2 = 0 hour IXOPT2 = 1 day IXOPT2 = 2 Min IXOPT2 = 3 sec IXOPT2 = 4 msec Setting of units when X axis represents burnup (IXOPT = 4 or 6) (Dummy when IXOPT is neither 4 nor 6) IXOPT2 =0 MWd tUO2 IXOPT2 =4 MWd tMOX IXOPT2 =2 MWd tU IXOPT2 =5 GWd tMOX IXOPT2 =1 GWd tUO2 IXOPT2 =6 MWd tHM
IXOPT2 =3 GWd tU IXOPT2 =7 GWd tHM IYOPT2 setting of units for time and burnup Setting of units when Y axis represents time (IYOPT(I)=1 or 12) IYOT2 =0 MWd tUO2 IYOPT2 =4 MWd tMOX IYOT2 =2 MWd tU IYOPT2 =5 GWd tMOX
IYOPT2 =1 GWd tUO2 IYOPT2 =6 MWd tHM IYOPT2 =3 GWd tU IYOPT2 =7 GWd tHM
IYNUM number of Y axes When more than 2 physical properties are set for Y axis
(IYNUM ≧2) IYNUM = IRNUM must be set since one graph is drawn for one Y axis (IYOPT(I) I = 1 IYNUM) select contents of Y axis from Tables 1 to 9 and input the
physical quantity number
(IYOPT(I) I=1 IRNUM) Input the IDNO number of physical quantity of Y axis selected from Table (1) to (3)
(Note) 1) Designation of IXOPT=19 has the same effect as that which is given by designation of IXOPT=8 or IXOPT2=4 and the time is in elapsed time (ms) 2) HM is the sum of weight of U and Pu in MOX fuel
5 (IR(I) I = 1 IRNUM) () Radial mesh number (IR(I) I = 1 IRNUM) radial mesh number is set for each figure When setting is not necessary input 1
JAEA-DataCode 2013-009
- 165 -
6
(IZ(I) I = 1 IRNUM) () Axial segment number (IZ(I) I = 1 IRNUM) Set the segment number in the axial direction for each figure Input 1 when setting is not necessary
7
(ITIM(I) I = 0 1) or (ITIM(I) I = 1 RNUM) () Time step number (When ITOPT = 0 input (ITIM(I) I = 12)) ITIM(1) = set a time step number for starting point of the figure ITIM(2) = set a time step number for end point of the figure (When ITOPT = 1 input (ITIM(I) I = 1 RNUM)) Set time step numbers for each figure (When ITOPT=3 input (ITIM(I) I=1 IRNUM)) Set the time of output Unit is specified by
IXOPT2 ITIM is a real number Example when IRNUM=3 IXOPT2=3 (unit is sec) and ldquoITIM(1)=00 ITIM(2)=10 ITIM(3)=20rdquo is input by Line No7 the plot program finds the history points which are given at the closest time to 00s 10sand 20s and outputs figures at these history points
8
X0 XM XNUM IXN IFLAG(6) () Setting of X-axis scale This line is a DUMMY when IXOPT=2 or 3 X0 minimum value of X-axis scale (IFLAGne3) XM maximum value of X-axis scale (IFLAGne3) XNUM increment of X-axis scale (IFLAGne3) IXN number of digits after decimal point on X axis (IFLAGne3) Example IXN = minus1 for 10 IXN = 1 for 100 IXN = 2 for 1000 IFLAG setting of X-axis scale =3 automatic scaling is applied to X axis ne3 X axis is drawn with designated scaling by input
9
IYNUM lines are required (I = 1 IYNUM) Y0(I) YM(I) YNUM(I) IYN(I) IFLAG(I) () Setting of Y-axis scale
Y0(I) minimum value of Y-axis scale YM(I) maximum value of Y-axis scale YNUM(I) increment of Y-axis scale IYN(I) number of digits after decimal point on Y axis (input in the same manner as for IXN) IFLAG(I) option for Y-axis scale = 0 scale is expressed with real numbers (decimal number expression) = 1 scale is expressed with floating format = 2 logarithmic scaling is used for Y axis = 3 automatic scaling is applied to Y axis
When IFLAG(I) = 3 Y0 to IYN are DUMMY since automatic scaling is selected When IFLAG(I)=2 user can designate a semi-logarithmic scaling For example if user
wants to plot with the Y-axis of 107 to 1013 scale range designate ldquoY0(I)=7 YM(I)=13 YNUM(I)=1rdquo where IYN(I) is dummy
Note 1) Data specified by asterisk () are input with free format
JAEA-DataCode 2013-009
- 166 -
62 Tables of IDNOs classified by variables
Table (1) Physical Quantities of Y axis (1) ()designated by IXOPT2
Group No Item Unit Std-Out
A Data regarding time and burnup
1 2 3
Rod average burnup Fission gas release rate Rod internal pressure
() ()
(MPa)
4 Plenum volume (cm3)
5
Pellet elongation (when IFEMRD=1) at the objective segment designated by IFEM)
()
6 7 8
Cladding elongation at plenum top (IFEMRD=1) Maximum change of cladding outer radius Average linear heat rate in the axial direction
() (microm)
(Wcm)
times
9 10
Average iodine concentration Maximum iodine concentration
(gcm2) (gcm2)
times
times
11 12 13
Average change in cladding outer radius Coolant inlet temperature Coolant pressure
(microm) (C)
(MPa)
times
times
14
Coolant velocity or mass flow rate (designated by input parameter)
(ms) or (kgcm2s)
times
15 Average fast neutron flux in the axial direction (1013ncm2s)
16 17 18
Average fast neutron fluence in the axial direction Pellet elongation (IFEMRD=0) Cladding elongation (IFEMRD=0)
(1020ncm2) () ()
19
Cladding max change of outer diameter at zero power state (IFEMRD=0)
(microm) times
20
Cladding average change of outer diameter at zero power state (IFEMRD=0)
(microm) times
21 22
Pellet elongation (IFEMRD=1) Cladding elongation at plenum top (IFEMRD=1)
(mm) (mm)
times
times
23 --- 28 Not used
29 30
Coolant mass flow rate He gas release rate
(kgm2s) ()
times
times
[Note] 1) Std-Out (Standard output states) indicates the default state of output O mark
= output X mark = not output They are standard output from FEMAXI by setting default
states of IDNO in making the plotter data file Regarding IDNO number items marked by times
eg pellet elongation when plotted output of pellet elongation is needed it is necessary to set
IDNO(21)=1 in input file of FEMAXI
2) When calculating a case with long power history in FEMAXI the size of the plot data file
sometimes becomes substantially large To avoid this unnecessary items among items
marked by should be set as IDNO()=0 Whereby the plot file size can be minimized Here
JAEA-DataCode 2013-009
- 167 -
indicates each item number in the figure
3) When IFEMRD=0 items 5 and 6 are elongations at the objective segment
4) IDNO=7 and 11 are the displacement at the outer surface of oxide of cladding When the
displacement at the metal part of cladding ie at the interface of metal-oxide IDNO=174
is used
Here IDNO=19 and 20 are results of 2-D local mechanical analysis In this analysis no
oxide layer is taken into account so that cladding outer radius displacement (metal-oxide
interface) is implicitly assumed to be equal to the displacement at outer oxide surface
When IFEMRD=1 ie entire rod length (ERL) mechanical analysis solely IDNO=17
to 20 which are used in the 2-D local mechanical analysis are given the results of ERL
analysis
JAEA-DataCode 2013-009
- 168 -
Table (2) Physical Quantities of Y axis (2) ()designated by IXOPT2 Group No Item Unit Std-Out
B1 Data regarding time burnup
and axial location
41 Linear heat rate (thermal analysis=TA) (Wcm)
42 Burnup (TA) ()
43 Diameter gap width (mechanical analysis when IFEMRD=0 gap at each axial segment and when IFEMRD=1 gap at each node couple is output sequentially)
(microm) times
44 45
PCMI contact pressure (When IFEMRD=0) Fission gas release rate
(MPa) ()
times
46 Frictional force between pellet and cladding in the axial direction (When IFEMRD=0)
(MPa) times
47 Pellet elongation (When IFEMRD=0) () times
48
Cladding elongation (Items 47 and 48 are output by the mechanical analysis When IFEMRD=0 elongation at each axial segment is obtained when IFEMRD=1 the same values in the axial direction are output)
() times
49 50 51 52 53 54
Gap conductance (TA) Coolant temperature (TA) Cladding inner surface temperature (TA) Cladding outer surface temperature (TA) Pellet center temperature (TA) Pellet outer surface temperature (TA)
(Wcm2C) (C) (C) (degC) (degC) (degC)
times times times
55 56 57 58 59 60
Cladding outer radius change(the same as 43) Composition of Xe + Kr (TA) Pellet density (TA) Cladding metal-oxide interface temperature Cladding outer oxide layer thickness Coolant enthalpy
(microm) ()
(TD) (C)
(microm) (kJkg)
times times times times
61 62 63 64 65
Coolant quality Cladding outer surface heat flux Cladding outer surface heat transfer coefficient Fast neutron flux Fast neutron fluence
(-) (Wcm2)
(Wcm2C) (1013ncm2s) (1020ncm2)
times times times
66 67 68 69
Pellet power density Gap size Pellet densification strain (ΔVV) Rim thickness
(Wcm3) (microm)
(001) (microm)
70 Additional FGR from rim structure ()
Note 1) When the 2-D local mechanical analysis is performed (IFEMRD=0) items 47 and 48 are uniform values in the axial direction and items 43 44 46 55 and 68 are the values which are obtained with respect to half a pellet length of the objective segment The others are obtained with respect to the 1-D entire rod length mechanical analysis (IFEMRD=1) 2) IDNO=55 cladding outer diameter displacement (metal-oxide interface) = displacement at outer oxide surface
JAEA-DataCode 2013-009
- 169 -
Table (3) Physical Quantities of Y axis (3) Group No Item Unit Std-
Out
B2 Data regarding time burnup
and axial location
71 72 73 74 75
Molar quantity of released Xe Molar quantity of released Kr Molar quantity of released He Contact pressure in the radial direction (IFEMRD=1) Frictional force in the axial direction (IFEMRD=1)
(001mol) (001mol) (001mol) (MPa) (MPa)
times times times
times
76 77 78 79 80
Pellet elongation (IFEMRD=1) Cladding elongation (IFEMRD=1) Cladding outer oxide surface diameter change (IFEMRD=1) Pellet porosity deignated by IPDENS Pellet volume change deignated by IPDENS
() ()
(microm) () ()
times
times
times
times
times
81 82 83 84 85
Pellet diameter change (IFEMRD=1) Pellet diameter strain (IFEMRD=1) Pellet-clad bonding progress ( 0 BD 1le le ) Intra-granular gas bubble radius (average) Volumetric strain by intra-granular gas bubbles(average)
(microm) () ( - ) ( o
A ) ()
times
times
times
times
times
86 87 88 89 90
Inter-granular gas bubble radius (average) Volumetric strain by inter-granular gas bubbles(average) Pellet radial displacement (IFEMRD=1) Elastic component of pellet radial displacement Thermal component of pellet radial displacement
(microm) ()
(microm) (microm) (microm)
times
times
times times times
91 92 93 94 95
Relocation component of pellet radial displacement Densification component of pellet radial displacement Swelling component of pellet radial displacement Creep component of pellet radial displacement Pellet axial displacement
(microm) (microm) (microm) (microm) (microm)
times
times times times times
96 97 98 99 100
Cladding inner surface radial displacement Elastic component of cladding radial displacement Thermal component of cladding radial displacement Creep component of cladding radial displacement Cladding axial displacement
(microm) (microm) (microm) (microm) (microm)
times times
times times times
(Note) The items 88 to 100 are obtained with respect to entire rod length (IFEMRD=1)
JAEA-DataCode 2013-009
- 170 -
Table (4) Physical Quantities of Y axis (4) ()designated by IXOPT2 Group NO Item Unit Std-
Out C1 Data regarding time burnup locations in the axial and radial directions
101 102 103 104 105
Pellet local burnup Pellet power density Pellet node temperature Cladding node temperature Pellet element temperature
() (Wcm3)
(C) (C) (C)
106 107 108 109 110
Cladding element average temperature Fission gas release rate Pellet grain diameter Pellet equivalent stress Pellet average stress
(C) ()
(microm) (MPa) (MPa)
times times times times
111 112 113 114 115
Pellet stress in the radial direction Pellet stress in the circumferential direction Pellet stress in the axial direction Pellet strain in the radial direction Pellet strain in the circumferential direction
(MPa) (MPa) (MPa)
() ()
times times times times times
116 117 118 119 120
Pellet strain in the axial direction Pellet elastic strain in the radial direction Pellet elastic strain in the circumferential direction Pellet elastic strain in the axial direction Pellet thermal expansion strain in the radial direction
() () () () ()
times times times times times
121 122 123 124 125
Pellet thermal expansion strain in the axial direction Pellet densification volumetric strain(ΔVV) Pellet swelling strain(ΔLL) Pellet equivalent creep strain Pellet creep strain in the axial direction
() () () () ()
times times times times times
126 127 128 129 130
Pellet creep strain in the axial direction Pellet creep strain in the axial direction Pellet equivalent plastic strain Pellet plastic strain in the radial direction Pellet plastic strain in the circumferential direction
() () () () ()
times times times times times
131 132 133 134 135
Pellet plastic strain in the axial direction Pellet displacement in the radial direction Pellet displacement in the axial direction Pellet radial displacement by elastic strain Pellet axial displacement by elastic strain
() (microm) (microm) (microm) (microm)
times times times times times
136 137 138 139 140
Pellet radial displacement by thermal strain Pellet axial displacement by thermal strain Pellet radial displacement by densification Pellet axial displacement by densification Pellet radial displacement by swelling
(microm) (microm) (microm) (microm) (microm)
times times times times times
(Note) When the local mechanical analysis is performed (IFEMRD=0) values of stress strain and displacement are obtained with respect to half a pellet length of the objective segment When entire rod length mechanical analysis is performed (IFEMRD=1) they are obtained with respect to the entire rod length
JAEA-DataCode 2013-009
- 171 -
Table (5) Physical Quantities of Y axis (5) ()designated by IXOPT2 Group No Item Unit Std-
Out
C2
Data regarding time burnup locations in the axial and radial directions
141 142 143 144 145
Pellet axial displacement by swelling Pellet radial displacement by creep Pellet axial displacement by creep Pellet radial displacement by plastic strain Pellet axial displacement by plastic strain
(microm) (microm) (microm) (microm) (microm)
times times times times times
146 147 148 149 150
Radius of intra-granular gas bubble Volumetric strain by intra-granular gas bubble Radius of inter-granular gas bubble Volumetric strain by inter-granular gas bubble Absolute value of pellet yield stress
( A )
() (microm) ()
(MPa)
times times times times times
151 152 153 154 155
Cladding equivalent stress Cladding average stress Cladding stress in the radial direction Cladding stress in the circumferential direction Cladding stress in the axial direction
(MPa) (MPa) (MPa) (MPa) (MPa)
times times times
156 157 158 159 160
Cladding strain in the radial direction Cladding strain in the circumferential direction Cladding strain in the axial direction Cladding elastic strain in the radial direction Cladding elastic strain in the circumferential direction
() () () () ()
times times times times
161 162 163 164 165
Cladding elastic strain in the axial direction Cladding thermal strain in the radial direction Cladding thermal strain in the axial direction Cladding average axial thermal strain (Note) Cladding axial irradiation growth strain
() () () () ()
times times times times
166 167 168 169 170
Cladding equivalent creep strain Cladding creep strain in the radial direction Cladding creep strain in the circumferential direction Cladding creep strain in the axial direction Cladding equivalent plastic strain
() () () () ()
times times times times
171 172 173 174 175
Cladding plastic strain in the radial direction Cladding plastic strain in the circumferential direction Cladding plastic strain in the axial direction Cladding radial displacement Sum of cladding axial displacements in each segment
() () ()
(microm) (microm)
times times
176 177 178 179 180
Cladding radial displacement by elastic strain Cladding axial displacement by elastic strain Cladding radial displacement by thermal strain Cladding axial displacement by thermal strain Cladding axial displacement by irradiation growth strain
(microm) (microm) (microm) (microm) (microm)
(Note1) Cladding average thermal strain of item 159 is obtained with respect to time burnup and radial location (Note2) The above table represents the data of both the mechanical analysis and thermal analysis for the entire length model The data of the average thermal strain in the axial direction of the cladding 164 represent those with respect to time burnup and the location in the radial direction
JAEA-DataCode 2013-009
- 172 -
Table (6) Physical Quantities of Y axis (6) Group No Item Unit Std-
Out
C2
Data regarding time burnup locations in the axial and radial directions
181 182 183 184
Cladding radial displacement by creep strain Cladding axial displacement by creep strain Cladding radial displacement by plastic strain Cladding axial displacement by plastic strain
(microm) (microm) (microm) (microm)
185 186 187
Number of generated fission gas atoms per unit volume of fuel Number of fission gas atoms per unit volume inside grain Number of fission gas atoms per unit volume of solid matrix
(atomscm3) (atomscm3) (atomscm3)
times times times
188 Number of fission gas atoms in the intra-grain bubbles per unit volume of fuel
(atomscm3) times
189 190
Number of intra-grain bubbles per unit volume Number of fission gas atoms per unit area of grain surface
bubblescm3 (atomscm2)
times times
191
Saturation number of fission gas atoms per unit area of grain surface
(atomscm2) times
192 193 194
Number of gas bubbles per unit area of grain surface Coverage fraction of inter-granular bubbles on grain surface Saturation radius of inter-granular gas bubble
bubblescm2 (-) (microm)
times times times
195 196 197
Nominal diffusion coefficient of fission gas atoms Effective diffusion coefficient of fission gas atoms Pellet theoretical density designated by IPDENS
(cm2s) (cm2s) (TD)
times times times
198 --- 200 Not used
201 Difference between element-average temperature of cladding and cladding outer surface temperature (oC) times
202 --- 222 Not used 223 Pellet yield stress (MPa) times 224 Cladding yield stress (MPa) times
225 --- 227 Not used 228 229 230
Pellet relocation strain in the radial direction Pellet relocation strain in the hoop direction Pellet relocation strain in the axial direction
() () ()
times times times
231 232
Pellet radial displacement induced by relocation Pellet axial displacement induced by relocation
(microm) (microm)
times times
233 Cladding outer surface displacement by waterside oxidation (microm) times 234 Pellet densification strain + swelling strain () 235 Apparent stiffness of pellet in the radial direction (GPa) 236 Apparent stiffness of pellet in the circumferential direction (GPa) 237 Apparent stiffness of pellet in the axial direction (GPa) 238 Youngrsquos modulus of cladding (GPa) 239 Poissonrsquos ratio of cladding (-) 240 Strain-hardening exponent of cladding (-) 241 Youngrsquos modulus of pellet (GPa) 242 Poissonrsquos ratio of pellet (-) 243 Thermal conductivity of cladding (WcmK) 244 Specific heat of pellet (JkgK) 245 Specific heat of cladding (JkgK) 246 Pellet melting point depending on the axial position (ordmC) 247 Gap size depending on the radial and axial positions (microm) 248 Deviation stress of cladding in the radial direction (MPa) 249 Deviation stress of cladding in the circumferential direction (MPa) 250 Deviation stress of cladding in the axial direction (MPa)
JAEA-DataCode 2013-009
- 173 -
Table (7) Physical Quantities of Y axis (7) (Note) Number of radial elements of IDNO=251- 300 depends on the designation of MESH
Group No Item Unit Std-Out
C2
Data regarding time burnup locations in the axial and radial directions
251 252 253 254
Fuel pellet local burnup Fuel pellet effective burnup Pellet ring element average temperature Fuel pellet thermal conductivity
(MWdt) (MWdt)
(oC) (WcmK)
times times times times
255 256
Cladding heat generation density by γ-heating Fraction of rim structure volume ( vX ratio)
(Wcm3) (-)
times times
257 Total porosity of fuel (0
0 0
swg densV Vp pV V
∆ ∆= + + ) () times
258 259 260
Rim structure porosity Open porosity in rim structure Porosity by fission gas bubbles
() () ()
times times times
261 Total volumetric swelling of pellet () times
262 263 264 265
Re-dissolution ratio b of fission gas atoms into solid matrix Re-dissolution ratioαinto solid matrix in rate-law model Fraction of gas atoms trapped by intra-granular gas bubbles g Stiffness fraction of dish element (buffer space)
(1s) (1s) (1s) (-)
times times times times
266 267
Displacement of pellet solid elements in the axial direction Volumetric fraction of dish space element to the initial value
(microm) (-)
times times
268 Not used
269 Ratio of amount of fission gas atoms in intra-grain gas bubbles to the total amount of generated fission gas atoms () times
270 Fission gas atoms in grain boundary gas bubbles in unit volume of pellet (atomscm3) times
271 Grain boundary inventory of fission gas atoms (atoms) times
272 Number density of grain boundary gas bubbles in pellet (bubblescm3) times
273 Ratio of amount of fission gas in grain boundary gas bubbles to the total amount of generated fission gas atoms () times
274 Fission gas atoms density inside the pores in rim structure (atomscm3) times
275 Grain diameter of fuel pellet (microm) times
276 277
Volumetric swelling of gas pores in rim structure --------- Not used -------------
()
times
278 Heat generation density of fuel pellet (Wcm3) times
279 280 281
Nodal temperature of pellet ring element Amount of released gas atoms per unit volume of pellet Pellet theoretical density designated by IPDENS=1
(oC) (atomscm3)
(TD)
times times times
282 283 284
Pellet theoretical density designated by IPDENS=2 Pellet theoretical density designated by IPDENS=3 Pellet theoretical density designated by IPDENS=4
(TD) (TD) (TD)
times times times
285 Ratio of amount of fission gas atoms retained in the solid phase of rim structure (-) times
286
Fraction of transferred amount of gas atoms from solid phase of rim structure to gas pores
(-) (cm2s)
times times
287 288
Nominal diffusion coefficient of He gas atoms (when HER=3) Effective diffusion coefficient of He gas atoms (when HER=3) (cm2s) times
times 289 -------------- Not used -----------------
290 He gas atoms generation rate per unit volume of fuel pellet (atomscm3s) times
JAEA-DataCode 2013-009
- 174 -
Table (8) Physical Quantities of Y axis (8) ()designated by IXOPT2
[Note] Number of radial elements of IDNO=251- 300 depends on the designation of MESH IDNO=301- 324 are of the data of 2-D local mechanical analysis They are output only when IFEMRD=0 Stress strain and displacement correspond to the values in half a pellet length geometry
Group IDNO Item Unit Std-Out
C2
Data regarding time burnup locations in the axial and radial directions
291 Internal pressure of grain boundary gas bubble (MPa) times
292 Overpressure of grain boundary gas bubbles (MPa) times
293 Intra-grain gas bubble pressure (MPa) times 294 Number density of He gas atoms at grain boundary (atomscm3) times
295 -296 - - - - - Not used - - - - -
297 He atoms density inside grain (when HER=3) (atomscm3) times
298 Average density of He atoms inside grain (when HER=3) (atomscm3) times 299 He gas release rate (when HER=3) () times 300 Void fraction of coolant water (-) times 301 Local burnup () 302 Heat generation density of fuel pellet (Wcm3) 303 Nodal temperature of pellet ring element (oC) 304 Nodal temperature of cladding ring element (oC) 305 Pellet element average temperature (oC) 306 Cladding element average temperature (oC) times 307 Fission gas release rate () 308 Pellet grain diameter (microm) times 309 Pellet equivalent stress (MPa) times 310 Pellet average (hydrostatic) stress (MPa) times 311 Pellet stress in the radial direction (MPa) times 312 Pellet stress in the circumferential direction (MPa) times 313 Pellet stress in the axial direction (MPa) times 314 Pellet strain in the radial direction () times 315 Pellet strain in the circumferential direction () times 316 Pellet strain in the axial direction () times 317 Pellet elastic strain in the radial direction () times 318 Pellet elastic strain in the circumferential direction () times 319 Pellet elastic strain in the axial direction () times 320 Pellet thermal strain I the radial direction () times 321 Pellet thermal strain in the axial direction () times 322 Pellet densification volumetric strain (ΔVV) () times 323 Pellet swelling strain (ΔLL) () times 324 Pellet equivalent creep strain () times 325 Pellet creep strain in the radial direction () times 326 Pellet creep strain in the circumferential direction () times 327 Pellet creep strain in the axial direction () times 328 Pellet equivalent plastic strain () times 329 Pellet plastic strain in the radial direction () times 330 Pellet plastic strain in the circumferential direction () times 331 Pellet plastic strain in the axial direction () times 332 Pellet radial displacement (microm) times
JAEA-DataCode 2013-009
- 175 -
Table (9) Physical Quantities of Y axis (9) IDNO=325- 365 are of the data of 2-D local mechanical analysis They are output only when IFEMRD=0 Stress strain and displacement correspond to the values in half a pellet length geometry
Group IDNO Item Unit Std-Out
C3
Data regarding time burnup locations in the axial and radial directions
333 Pellet axial displacement (microm) times 334 Pellet radial displacement by elastic strain (microm) times
335 Pellet axial displacement by elastic strain (microm) times 336 Pellet radial displacement by thermal strain (microm) times 337 Pellet axial displacement by thermal strain (microm) times 338 Pellet radial displacement by densification (microm) times 339 Pellet axial displacement by densification (microm) times 340 Pellet radial displacement by swelling (microm) times 341 Pellet axial displacement by swelling (microm) times 342 Pellet radial displacement by creep (microm) times 343 Pellet axial displacement by creep (microm) times 344 Pellet radial displacement by plastic strain (microm) times 345 Pellet axial displacement by plastic strain (microm) times
346 347348 349 350
Cladding equivalent stress Cladding average stress Cladding stress in the radial direction Cladding stress in the circumferential direction Cladding stress in the axial direction
(MPa) (MPa) (MPa) (MPa) (MPa)
times times times
351 352 353 354 355
Cladding strain in the radial direction Cladding strain in the circumferential direction Cladding strain in the axial direction Cladding elastic strain in the radial direction Cladding elastic strain in the circumferential direction
() () () () ()
times times times times
356 357 358 359 360
Cladding elastic strain in the axial direction Cladding thermal strain in the radial direction Cladding thermal strain in the axial direction Cladding average axial thermal strain (Note) Cladding axial irradiation growth strain
() () () () ()
times times times times
361 362 363 364 365
Cladding equivalent creep strain Cladding creep strain in the radial direction Cladding creep strain in the circumferential direction Cladding creep strain in the axial direction Cladding equivalent plastic strain
() () () () ()
times times times times
JAEA-DataCode 2013-009
- 176 -
Table (10) Physical Quantities of Y axis (10)
[Note] IDNO=366-400 are results in the case of ldquoIFEMRD=0rdquo ie in the 2-D Local
PCMI analysis Stress strain and displacement are values for the half-length pellet geometry
Group IDNO Item Unit Std-Out
C4
Data regarding time burnup locations in the axial and radial directions
366 Cladding plastic strain in the radial direction ()
367 368
Cladding plastic strain in the circumferential direction Cladding plastic strain in the axial direction
() ()
times times
369 370
Cladding radial displacement Cladding axial displacement
(microm) (microm)
371 372 373 374
Cladding radial displacement by elastic strain Cladding axial displacement by elastic strain Cladding radial displacement by thermal strain Cladding axial displacement by thermal strain
(microm) (microm) (microm) (microm)
375 376 377 378 379
Cladding axial displacement by irradiation growth strain Cladding radial displacement by creep strain Cladding axial displacement by creep strain Cladding radial displacement by plastic strain Cladding axial displacement by plastic strain
(microm) (microm) (microm) (microm) (microm)
380 Pellet yield stress (MPa) times
381 Cladding yield stress (MPa) times
382 Pellet relocation strain in the radial direction () times
383 Pellet relocation strain in the hoop direction () times
384 Pellet relocation strain in the axial direction () times
385 Pellet radial displacement induced by relocation (microm) times
386 Pellet axial displacement induced by relocation (microm) times
387 Cladding outer surface displacement caused by waterside oxidation
(microm) times
388 Pellet radial displacement calculated from strain (microm) times
389 Pellet axial displacement calculated from strain (microm) times
390 Cladding radial displacement calculated from strain (microm) times
391 Cladding axial displacement calculated from strain (microm) times
392 Pellet nodal coordinate value in the radial direction (mm) times
393 Pellet nodal coordinate value in the axial direction (mm) times
394 Cladding nodal coordinate value in the radial direction (mm) times
395 Cladding nodal coordinate value in the axial direction (mm) times
396 Densification and swelling strains of pellet () times
397 Shear stress in pellet (MPa) times
398 Shear stress in cladding (MPa) times
399 Shear strain in pellet () times
400 Shear strain in cladding () times
JAEA-DataCode 2013-009
- 177 -
Table (11) Physical Quantities of Y axis (11)
Group IDNO Item Unit Std-Out
A
Data regarding time and burnup
401 Plenum volume at zero power state (cm3) times 402 Pellet elongation at zero power state (IFEMRD=1) () times
403 Cladding max change of outer diameter at zero power state (IFEMRD=1)
(microm)
times
404 Cladding average change of outer diameter at zero power state (IFEMRD=1)
(microm)
times
405 Cladding elongation at zero power state (IFEMRD=1) () times
406 Cladding internal pressure at zero power state (MPa) times
407 Pellet elongation at zero power state (IFEMRD=0) () times
408 Cladding max change of outer diameter at zero power state (IFEMRD=0)
(microm)
times
409
Cladding average change of outer diameter at zero power state (IFEMRD=0)
(microm)
times
410 Cladding elongation at zero power state (IFEMRD=0) () times
411 - 420 - - - - - Not used - - - - - -
Table (12) Physical Quantities of Y axis (12)
Group IDNO Item Unit Std-
Out B Data
regarding time
burnup and axial elevation
421 Diametral gap size at zero power state (IFEMRD=0) (microm) times
422 PCMI pressure at zero power state(IFEMRD=0) (MPa) times
423 Pellet elongation at zero power state(IFEMRD=0) () times
424 Cladding elongation at zero power state(IFEMRD=0) () times
425 Cladding outer diameter change at zero power (IFEMRD=0) (microm) times
426 Pellet density at zero power state (TD) times
427 Diametral gap size by thermal model at zero power state (IFEMRD=1)
(microm) times
428 PCMI pressure at zero power state(IFEMRD=1) (MPa) times
429 Pellet elongation at zero power state(IFEMRD=1) () times
430 Cladding elongation at zero power state(IFEMRD=1) () times
431 Cladding outer diameter change at zero power (IFEMRD=1)
(microm) times
432 - 450 - - - - - Not used - - - - - -
(Note) When IZEROgt0 the Std-Out is O (output) for all the items of 401 to 406 and 421 to 427
JAEA-DataCode 2013-009
- 178 -
Table (13) Physical Quantities of Y axis (13)
(Note) When IZEROgt0 the Std-Out is O (output) for all the items of 451 to 465 The data 451-465 are for the entire rod length mechanical analysis irrespective of IFEMRD
Group IDNO Item Unit Std-
Out C Data
regarding time
burnup axial and radial locations
451 452 453
Pellet radial strain at zero power state Pellet circumferential strain at zero power state Pellet axial strain at zero power state
() () ()
times times times
454 455 456
Pellet swelling strain at zero power state Pellet radial displacement at zero power state Pellet axial displacement at zero power state
() (microm) (microm)
times times times
457 Pellet radial displacement by swelling at zero power state (microm) times
458 459 460 461
Pellet axial displacement by swelling at zero power state Cladding radial strain at zero power state Cladding circumferential strain at zero power state Cladding axial strain at zero power state
(microm) () () ()
times times
times times
462 Cladding axial strain by irradiation growth at zero power state () times
463 464
Cladding radial displacement at zero power state Cladding axial displacement at zero power state
(microm) (microm)
times
times 465
Cladding axial displacement by irradiation growth at zero power state
(microm) times
466 ndash470 - - - - - Not used - - - - - -
471 472 473
Pellet radial strain at zero power state Pellet circumferential strain at zero power state Pellet axial strain at zero power state
() () ()
times times times
474 475 476
Pellet swelling strain at zero power state Pellet radial displacement at zero power state Pellet axial displacement at zero power state
() (microm) (microm)
times times times
477 Pellet radial displacement by swelling at zero power state (microm) times
478 Pellet axial displacement by swelling at zero power state (microm) times 479 480 481
Cladding radial strain at zero power state Cladding circumferential strain at zero power state Cladding axial strain at zero power state
() () ()
times times times
482 Cladding axial strain by irradiation growth at zero power state () times 483 484
Cladding radial displacement at zero power state Cladding axial displacement at zero power state
(microm) (microm)
times
times
485 Cladding axial displacement by irradiation growth at zero power state
(microm) times
486 ndash500 - - - - - Not used - - - - - -
JAEA-DataCode 2013-009
- 179 -
Table (14) Physical Quantities of Y axis (14) [Note] Number of radial elements of IDNO=501 - 600 depends on the designation of MESH
Group DNO Item Unit Std-Out
C Data
regarding time
burnup axial and radial locations
501 Amount of He generation per unit volume of pellet (atomscm3) times 502
-508 - - - - - Not used - - - - - -
509 He partial pressure in plenum as a function of time and burnup (MPa) times
510 He gas density in plenum as a function of time and burnup (atomscm3
) times
511 -512 - - - - - Not used - - - - - -
513 Plenum gas temperature as a function of time and burnup (oC) times
514 -529 - - - - - Not used - - - - - -
530 Internal pressure at each axial segment as a function of time burnup and axial coordinate MPa times
531-533 - - - - - Not used - - - - - -
534 Segment averaged amount of He generation as a function of time burnup and axial coordinate (atomscm3) times
535 Segment averaged release rate of He as a function of time burnup and axial coordinate () times
536 Number of generated He atoms at each axial segment as a function of time burnup and axial coordinate (atoms) times
537-540 - - - - - Not used - - - - - -
541 Pellet shear creep strain (2-D local mechanical model) () times 542 Pellet shear plastic strain (2-D local mechanical model) () times 543 Pellet shear elastic strain (2-D local mechanical model) () times 544 Pellet shear relocation strain (2-D local mechanical model) () times 545 Cladding shear creep strain (2-D local mechanical model) () times 546 Cladding shear plastic strain (2-D local mechanical model) () times 547 Cladding shear elastic strain (2-D local mechanical model) () times 548 Heating steam layer temperature (Dry-out model) (oC) times
549 Flow inner tube temperature (Dry-out model) (oC) times
550 He gas layer temperature (Dry-out model) (oC) times
551 Flow outer tube temperature (Dry-out model) (oC) times
552 Circulating water temperature (Dry-out model) (oC) times
553 Capsule outer mantle pipe temperature (Dry-out model) (oC) times
554-555 - - - - - Not used - - - - - -
JAEA-DataCode 2013-009
- 180 -
Table (15) Physical Quantities of Y axis (15) [Note] Number of radial elements of IDNO=501 - 600 depends on the designation of MESH
Group IDNO Item Unit Std-Out
C Data
regarding time
burnup axial and
radial ocations
556 Axial coordinate of top height of buffer element of each axial segment (mm) times
557 Axial coordinate of top height of pellet stack of each axial segment (mm) times
558 - - - - - -Not used - - - - - - - -
559 Pellet stack total (elastic+plastic) elongation excluding thermal expansion component () times
560 Cladding total (elastic+plastic) elongation excluding thermal expansion component () times
561 Volume of released fission gas at 1 atm 0 oC (mm3) times 562 Volume of released He gas at 1atm 0oC (mm3) times
563 Pellet peak temperature highest temperature of pellet stack ring element at a certain axial segment (oC) times
564 Location of peak temperature the radial coordinate value of mid-thickness of pellet stack ring element having the highest temperature IDNO=563 in a certain axial segment
(mm) times
565 Average hydrogen concentration H in cladding (wtppm) times
566 Pre-crack depth a1 (derived from the least square approximation curve of data of high burnup PWR fuels subjected to the NSRR experiments)
(microm) times
567 Pre-crack depth a2 (derived from an upper envelope curve of data of high burnup PWR fuels subjected to the NSRR experiments )
(microm) times
568 Effective fast neutron fluence (ncm2) times 569 Coefficient of cladding cold-work (-) times 570 Cladding temperature used to evaluate IDNO=568 and 569 (oC) times
571 Cladding temperature change rate used to evaluate IDNO=568 and 569 (oCs) times
572 Gas phase volume of plenum (cm3) times
573 Ratio of amount of fission gas atoms retained inside grains to the total generation of fission gas atoms () times
574 Ratio of amount of fission gas atoms retained at grain boundary to the total generation of fission gas atoms () times
575 -582 - - - - - Not used - - - - - -
583 Temperature at the most-heated segment of cladding () times
584 -592 - - - - - Not used - - - - - -
593 Additional FGR from rim structure (depending on the radial element and axial segment) () times
594 Ratio of amount of fission gas atoms generated in rim structure to the total amount of generated fission gas atoms in pellet (depending on the radial element and axial segment)
() times
595 - 598 - - - - - Not used - - - - - -
599 Critical heat flux (Wcm2) times 600 - - - - - Not used - - - - - -
JAEA-DataCode 2013-009
- 181 -
Table (16) Physical Quantities of Y axis (16) [Note] Number of radial elements of IDNO=701 - 708 depends on the designation of MESH
Group IDNO Item Unit Std-Out
C
Data regarding time burnup axial and radial locations
701 Ratio of amount of fission gas atoms retained in solid phase to the total amount of generated fission gas atoms for each axial segment
() times
702 Ratio of amount of fission gas atoms in rim pores to the total amount of generated fission gas atoms for each axial segment () times
703 Ratio of amount of fission gas atoms in grain boundary bubbles to the total amount of generated fission gas atoms for each axial segment
() times
704 Ratio of amount of fission gas atoms in grain boundary bubbles to the total amount of generated fission gas atoms in a rod () times
705 Ratio of amount of fission gas atoms in rim pores to the total amount of generated fission gas atoms in a rod () times
706 Ratio of amount of fission gas atoms retained in solid phase to the total amount of generated fission gas atoms in a rod () times
707 Ratio of amount of fission gas atoms in intra-grain gas bubbles to the total amount of generated fission gas atoms in a rod () times
708 Ratio of amount of fission gas atoms retained inside pellets to the total amount of generated fission gas atoms in a rod () times
JAEA-DataCode 2013-009
- 182 -
63 Plotting the quantities with common Y-axis To plot the following data in a single picture IYNUM=1 is to be designated so that Y-
axis is drawn by a common scale
Physical quantity of Y-axis IDNO Burnup 1 42 101
Fission gas release rate 2 45 70 107 255 573 574 Rod internal pressure 3 406 Rod internal free volume 4 401 572 Elongations of pellet and cladding 5 6 17 18 47 48 402 405 423 424 Cladding outer diameter change 7 11 19 20 55 78 403 404 425 431 Pellet stack displacement in the axial direction 133 266
Linear heat rate 8 41 Iodine concentration 9 10 Temperature 12 50 51 52 53 54 58 Gap size 43 67 421 427 PCMI pressure 44 46 422 428 Molar amount of released fission gas 71 72 73 Stress 109-113 309-313 Strain 114-131 156-173 451-454 459-462 Displacement 132-145 174-184 455-458 463-465 Radius of inter-granular gas bubble 148194 Number density of gas atoms in grain 185-188 264 - 266 270 274 Surface number density of gas atoms in grain boundary 190 191 Diffusion constant of fission gas atoms 195196 Pellet temperature 53 54 103 105 253 279 303 305 Cladding temperature 51 52 58 104 106 304 306 Cladding deviation stress 248 - 250 Fast neutron fluence 16 65 568
Example Specifying the IRNUM=number of plotted figures and IYNUM=1
401 the first ldquo4rdquo is IRNUM the number of figures 133151525354 fuel temperature the fourth ldquo1rdquo is IYNUM the number of Y-axis 1111 Specifying the radial ring number 1111 Specifying the axial segment number 11000 00 30 05 13 2780 28801003 ldquoIYNUM=1rdquo allows only one line for Y-axis scale
JAEA-DataCode 2013-009
- 183 -
64 Explanation on the physical quantities of Y-axis (3) (4) C Group
In the following explanation thermal analysis is identical irrespective of IFEMRD value
designated by input Also fission gas release rate (Item No107) is an exception of the explanation because it is always output at each axial segment
641 Physical quantities of pellet (1) In thermal analysis and ERL mechanical analysis
Displacement stress strain etc are evaluated at points indicated bytimesmarks which are the Gaussrsquos integral (Gaussian) points Here temperature is either the value at node or element average value When assigning the plotting positions IR and IZ assign the location of point in the radial and axial directions respectively Physical quantities evaluated at nodal points should be specified by IRrsquo=IR+1
When MESH=3 IR=1 to 36 and IZ= designated axial segments in both thermal analysis
and ERL mechanical analysis An example of ring element division of pellet stack is shown
in Fig61
[In case of 36 radial divisions] IR= 1 2 3 4 5 hellip 33 34 35 36
times times times times times times times times times times 8 (No of Axial
times times times times times times times times times times 7 segments
times times times times times times times times times times 6 ≦40)
times times times times times times times times times times 5
times times times times times times times times times times 4
times times times times times times times times times times 3
times times times times times times times times times times 2
times times times times times times times times times times IZ=1 Center line of Pellet Fig61 Numbering of elements and location of Gaussian points in the case where
pellet stack is divided into 36 ring elements in the radial direction and 8 segments in the axial direction
JAEA-DataCode 2013-009
- 184 -
(2) 2-D local mechanical analysis
Displacement stress strain etc are evaluated at points indicated bytimesmarks which are the Gaussrsquos integral (Gaussian) points Here temperature is either the value at node or element average value When assigning the plotting positions IR and IZ assign the location of point in the radial and axial directions respectively Physical quantities evaluated at nodal points should be specified by IRrsquo=IR+1
When MESH=3 and outputting the physical quantities of each element IR=1 to 36 (18 ring elements) and IZ=1 to 6 (three elements)
When MESH=3 and outputting the physical quantities at nodal points of each element IR=1 to 37 and IZ=1 to 7
An example of ring element division of half a pellet length is shown in Fig62
[In case of 18 radial elements] IR= 1 2 3 4 5 33 34 35 36
times times times times times times times times times times 6
times times times times times times times times times times 5
times times times times times times times times times times 4 Half a pellet length
times times times times times times times times times times 3
times times times times times times times times times times 2
times times times times times times times times times times 1=IZ
Center line of Pellet
Fig62 Numbering of elements and location of Gaussian points in the case where half a pellet geometry is divided into 18 ring elements in the radial direction and 5 elements in the axial direction
JAEA-DataCode 2013-009
- 185 -
642 Physical quantities of cladding
(1) Model 1 ERL mechanical analysis (IFEMRD=1) Displacement stress strain etc are evaluated at points indicated bytimesmarks which are
the Gaussrsquos integral (Gaussian) points Here temperature is either the value at node or element average value When assigning the plotting positions IR and IZ assign the location of point in the radial and axial directions respectively
A cladding with no Zr-liner has 10 ring elements consisting of 8 elements for metallic
part and 2 elements for outer surface oxide Accordingly with respect to Gaussian points and
temperatures IR=1 to 8 are for the metallic elements and IR=9 and 10 are for the outer oxide
However a cladding with Zr-liner has 12 ring elements consisting of 2 elements for Zr-
liner 8 elements for metallic part and 2 elements for outer surface oxide Accordingly with
respect to Gaussian points and temperatures IR=1 to 2 are for the Zr-liner elements IR=3 to
10 are for the metallic elements and IR=11 and 12 are for the outer oxide Physical quantities evaluated at nodal points should be specified by IRrsquo=IR+1
The standard setting of ring element division of cladding in the 1-D ERL and thermal
analyses is shown in Fig63
Standard setting (No of Axial segments≦40) IR= 1 2 3 4 5 6 7 8 9 10
times times times times times times times times times times IZ= 8
times times times times times times times times times times 7
times times times times times times times times times times 6
times times times times times times times times times times 5
times times times times times times times times times times 4
times times times times times times times times times times 3
times times times times times times times times times times 2
Inner surface times times times times times times times times times times 1
of cladding Metal Oxide Fig63 Numbering of elements and location of Gaussian points in the cladding segment
which has 8 ring elements of metal part and two outer oxide elements
JAEA-DataCode 2013-009
- 186 -
(2) Mode 2 3 2-D local mechanical analysis (IFEMRD=0) Stress strain etc evaluated at points indicated bytimesmarks which are the Gaussrsquos integral
points Here temperature is either the value at node or element average value Displacement is evaluated at nodal points and output
Fig64 shows an example which has 5 ring elements ie 4 metallic elements and one outer oxide element The inner element is ignored in the 2-D mechanical analysis
Here if cladding has Zr-liner the inner elements 1 and 2 is assigned to Zr-liner so that IR=1 and 2 are the Zr-liner elements IR=3 to 10 are metallic elements and IR=11 and 12 are outer oxide elements
Physical quantities evaluated at nodal points should be specified by both IRrsquo=IR+1 and IZrsquo=IZ+1
The standard setting of ring element division of cladding in the 2-D local mechanical
analysis is shown in Fig63
[In case of 5 radial elements] IR= 1 2 3 4 5 6 7 8 9 10
times times times times times times times times times times 6
times times times times times times times times times times 5
times times times times times times times times times times 4 Half a pellet length
times times times times times times times times times times 3
times times times times times times times times times times 2
times times times times times times times times times times 1=IZ
Metal Oxide Inner surface of cladding
Fig64 Numbering of elements and location of Gaussian points in the cladding segment
which corresponds to half a pellet length and has 4 ring elements of metal part one outer oxide ring element and 6 axial elements
JAEA-DataCode 2013-009
- 187 -
7 Sample InputOutput (numerical and plotted outputs)
71 FEMAXI-7 numerical output image of ldquoABC1outrdquo
FUEL ELEMENT MODELING BY AXI SYMMETRIC FINITE ELEMENT METHOD - - - --- - - - VERSION 11 MECHANICAL ANALISYS MODE WHOLE ROD (IFEMRD = 1) RUN DATE 13MAR04 START TIME 194833 ( INPUT FILE NAME = ft05d ) 1 I N P U T D A T A L I S T ------------------------------- 1 2 3 4 5 6 7 8 CARD NO 5050505050505050 1 PWR-type Rod Sample Case (January 2012) 2 ampINPUT IBUNP=1IDAY=1IRH=1 TROOM=2951 DTPL=200 ICORRO=2 PX=990 3 PITCH=16 IPUGH=1 TLIM=1000 IFLX=-2 INPRD=2 RCORRO=04 4 IRIM=1 RFGFAC=10 FRELOC=030 EPSRLZ=5D-3 IFSNT=1FAIW=5E11 5 IGRAIN=0 GR=100 GRWF=15 LBU=1 IPRO=0 R1=10 R2=10 ICAGRW=1 6 IHOT=1 BETAX=0002 ISPH=1 ICFL=1 IROD=0 7 8 IFEMRD=1 IFEMOP=2 IDSELM=1 IDENSF=0 DMAX=1020 FDENSF=0 9 IPEXT=14 IDCNST=1 IPTHCN=17 IFSWEL=4 A1=006 ICPLAS=3 10 IBOND=0 IGAPCN=5 BDX=100000 ALBD=07 FBONDG=10 SBONDG=001 11 MATXO=2 FACXO=01 01 01 100 01 12 CRPEQ=0 CRFAC=10 IPCRP=2 FCRFAC=10 IPTHEX=3 ATHEX=3561D-6 13 IRM=0 MESH=3 MOXP=0 IPLYG=1 IZYG=1 TCS=177315 IZOX=1 IST=1 14 15 IPRINT=11001 IPLOPT=5 DPBU=100 16 IWTHE=100190130 31 17 IWROD(1)=31 80 31 000100 18 IDNO(1)=81 60 51 200 19 IDNO(41)=101 01111 301 401101150130101 20 IDNO(81)=1 190 21 IDNO(101)=10 3101 30101101 601 801100 1130 22 IDNO(151)=20 61 30110101 3010011 401 210 23 ampEND 24 10 6 25 1 083 097 26 2 0 00 082 10 004 095 10 27 2 0 00 082 10 004 095 10 28 2 0 00 082 10 004 095 10 29 2 0 00 082 10 004 095 10 30 2 0 00 082 10 004 095 10 31 2 0 00 082 10 004 095 10 32 2 0 00 082 10 004 095 10 33 2 0 00 082 10 004 095 10 34 2 0 00 082 10 004 095 10 35 2 0 00 082 10 004 095 10 36 06218 0021 00 37 80 10 10 00 00 00 5500 00 38 23 39 00 01 55815 154 1 304 40 620 865 1000 1149 1190 1163 1005 0931 41 786 541 8 42 100 1145 43 150000 2500
JAEA-DataCode 2013-009
- 188 -
44 200000 2700 45 250000 2900 1 46 280000 2700 47 300000 2600 48 305000 1000 49 305010 10 1 50 656 903 1098 1167 1201 1174 1073 0959 51 817 581 8 52 305100 1000 53 350000 2000 1 54 400000 2200 55 420000 2100 56 460000 2050 57 490000 1900 58 500000 1800 59 500100 60 1 60 798 1002 1104 1128 1122 1104 1086 1032 61 912 708 7 62 501100 1700 1 63 520000 1600 64 550000 1500 65 570000 1400 66 598999 1100 55815 154 1 304 67 599000 1100 55815 154 1 304 68 STOP 5050505050505050 1 0---------------------------------------------------------------------------------- PWR-type Rod Sample Case (January 2012) ---------------------------------------------------------------------------------- INPUT DATA 0(1) PELLET SPECIFICATIONS ---- 0 NODE DIAMETER (CM) SHAPE U-235 FRACTIONAL ONE PELLET NODE INSIDE OUTSIDE CHAMF DISH ENRICH DENSITY LENGTH (CM) LENGTH (CM) 1 0000 0820 0040 0950 1000 10000 2 0000 0820 0040 0950 1000 10000 3 0000 0820 0040 0950 1000 10000 4 0000 0820 0040 0950 1000 10000 5 0000 0820 0040 0950 1000 10000 6 0000 0820 0040 0950 1000 10000 7 0000 0820 0040 0950 1000 10000 8 0000 0820 0040 0950 1000 10000 9 0000 0820 0040 0950 1000 10000 10 0000 0820 0040 0950 1000 10000 DISH DIAMETER (CM) = 0622 DISH DEPTH (CM) = 0021 DISH BOTTOM (CM) = 0000 PELLET TOTAL WEIGHT (GRAM) = 550000 GRAIN SIZE (MICRON) = 10000 MAXIMUM FRACTIONAL DENSITY = 0970 SATURATE BURNUP (MWDTUO2) = 20000000 (2) OTHERS CLAD MATERIAL IS STRESS RELIEVED ZIRCALOY CLAD INSIDE DIAMETER (CM) = 0830 CLAD OUTSIDE DIAMETER (CM) = 0970 THERMAL RELOCATION (-) = 0300 UPPER PLENUM VOLUME (CM3) = 8000 LOWER PLENUM VOLUME (CM3) = 0000 INITIAL GAS PRESSURE (MPA) = 1000 INITIAL GAS COMPOSITION (PERCENT) HELIUM = 1000 N2 = 00 KRYPTON = 00 XENON = 00 PELLET SURFACE ROUGHNESS (CM) = 00001 CLADDING SURFACE ROUGHNESS (CM) = 00001 ROOM TEMPERATURE (DEGK) = 29510 1 HISTORY DATA (1) STAGE TIME BURNUP LHR COOLANT COOLANT COOLANT FAST NEUTRON HISTRY PRINT SSUS NO TEMP PRESS VELOCITY FLUX OPTION OPTION OPTION (NHIST) (H M S MS) (MWDTUO2) (MWDTU) (GJKGU) (WCM) (DEGK) (MPA) (MS) (NCM2S) (0=OFF) (1=ON) (1=0N) ------- -------------- ---------------------------- ------- -------- ------- ---------- ------------ ------ ------ ------ 1 0 0 0 0 00 00 000 00 55815 1540 30400 5000D+09 0 1 0 2 201920424 88 100 086 1145 55815 1540 30400 5725D+13 0 0 0 3 95903137860 132222 150000 129600 2500 55815 1540 30400 1250D+14 0 0 0 4 11828 8 2729 176296 200000 172800 2700 55815 1540 30400 1350D+14 0 0 0 5 139055442965 220370 250000 216000 2900 55815 1540 30400 1450D+14 0 1 0 6 151523443106 246815 280000 241920 2700 55815 1540 30400 1350D+14 0 0 0 7 1603044 1696 264444 300000 259200 2600 55815 1540 30400 1300D+14 0 0 0 8 163535637288 268852 305000 263520 1000 55815 1540 30400 5000D+13 0 0 0 9 163561451942 268861 305010 263529 10 55815 1540 30400 5000D+11 0 1 0 10 1637659 3825 268940 305100 263606 1000 55815 1540 30400 5000D+13 0 0 0 11 198595338887 308519 350000 302400 2000 55815 1540 30400 1000D+14 0 1 0 12 226301552534 352593 400000 345600 2200 55815 1540 30400 1100D+14 0 0 0 13 237123830796 370222 420000 362880 2100 55815 1540 30400 1050D+14 0 0 0 14 259553826231 405481 460000 397440 2050 55815 1540 30400 1025D+14 0 0 0 15 27723 4 0609 431926 490000 423360 1900 55815 1540 30400 9500D+13 0 0 0
JAEA-DataCode 2013-009
- 189 -
16 28352 056896 440741 500000 432000 1800 55815 1540 30400 9000D+13 0 0 0 17 283643137758 440829 500100 432086 60 55815 1540 30400 3000D+12 0 1 0 18 284964457773 441710 501100 432950 1700 55815 1540 30400 8500D+13 0 1 0 19 298293257924 458370 520000 449280 1600 55815 1540 30400 8000D+13 0 0 0 20 320813533 18 484815 550000 475200 1500 55815 1540 30400 7500D+13 0 0 0 21 336862948372 502444 570000 492480 1400 55815 1540 30400 7000D+13 0 0 0 22 3638551 9574 528007 598999 517535 1100 55815 1540 30400 5500D+13 0 1 0 23 363855730374 528007 599000 517536 1100 55815 1540 30400 5500D+13 0 1 0 LAST STAGE NUMBER = 23 ---------------------------- HISTORY DATA LIST (MODIFIED BY RODBURN OUTPUT RESULT) 1 HISTORY DATA (1) STAGE TIME BURNUP LHR COOLANT COOLANT COOLANT FAST NEUTRON HISTRY PRINT SSUS NO TEMP PRESS VELOCITY FLUX OPTION OPTION OPTION (NHIST) (H M S MS) (MWDTUO2) (MWDTU) (GJKGU) (WCM) (DEGK) (MPA) (MS) (NCM2S) (0=OFF) (1=ON) (1=0N) ------- -------------- ---------------------------- ------- -------- ------- ---------- ------------ ------ ------ ------ 1 0 0 0 0 00 00 000 00 55815 1540 30400 4625D+09 0 1 0 2 201920424 82 93 080 1059 55815 1540 30400 5296D+13 0 0 0 3 95903137860 123995 140667 121536 2359 55815 1540 30400 1180D+14 0 0 0 4 11828 8 2729 165727 188010 162441 2565 55815 1540 30400 1282D+14 0 0 0 5 139055442965 207733 235664 203613 2773 55815 1540 30400 1386D+14 0 1 0 6 151523443106 233063 264399 228441 2591 55815 1540 30400 1296D+14 0 0 0 7 1603044 1696 250005 283620 245047 2502 55815 1540 30400 1251D+14 0 0 0 8 163535637288 254247 288432 249205 963 55815 1540 30400 4814D+13 0 0 0 9 163561451942 254256 288442 249213 10 55815 1540 30400 4815D+11 0 1 0 10 1637659 3825 254332 288528 249288 963 55815 1540 30400 4815D+13 0 0 0 11 198595338887 292666 332016 286862 1943 55815 1540 30400 9714D+13 0 1 0 12 226301552534 335695 380831 329038 2158 55815 1540 30400 1079D+14 0 0 0 13 237123830796 353018 400483 346017 2068 55815 1540 30400 1034D+14 0 0 0 14 259553826231 387863 440013 380171 2034 55815 1540 30400 1017D+14 0 0 0 15 27723 4 0609 414169 469856 405955 1896 55815 1540 30400 9478D+13 0 0 0 16 28352 056896 422972 479842 414583 1799 55815 1540 30400 8996D+13 0 0 0 17 283643137758 423060 479942 414670 60 55815 1540 30400 2999D+12 0 1 0 18 284964457773 423941 480941 415533 1699 55815 1540 30400 8497D+13 0 1 0 19 298293257924 440594 499834 431856 1599 55815 1540 30400 7997D+13 0 0 0 20 320813533 18 467028 529822 457766 1499 55815 1540 30400 7497D+13 0 0 0 21 336862948372 484651 549814 475039 1399 55815 1540 30400 6997D+13 0 0 0 22 3638551 9574 510203 578801 500084 1100 55815 1540 30400 5498D+13 0 1 0 23 363855730374 510203 578802 500085 1100 55815 1540 30400 5498D+13 0 1 0 LAST STAGE NUMBER = 23 ---------------------------- 1 OUTPUT ---STAGE--- 1 IFEM = 6 ---------------------------------------------------------------------------------------------------- |THERMAL ANALYSIS INFORMATION | | STAGE NO 1 | | TIME (HMSMS) 0 0 0 0 | | COOLANT TEMPERATURE 28500 DEGC | | COOLANT PRESSURE 154D+01 MPA | ---------------------------------------------------------------------------------------------------- LHR BURN UP GAP CONDUCTANCE (WCM2-K) TEMPERATURE (C) CLEARANCE CONTACT NODE (WCM) (MWDTU) TOTAL GAS SOLID RAD PC PS CI CO (MICRONS) FORCE(MPA) NODE 10 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 10 9 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 9 8 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 8 7 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 7 6 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 6 5 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 5 4 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 4 3 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 3 2 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 2 1 00 00 0602 0600 0000 00028 2850 2850 2850 2850 32314 0000 1 BURN UP PELLET DISPLACEMENT (MICRONS) CLADDING DISPLACEMENT (MICRONS) (FISSCC THERMAL DENSIFI IRRAD RELOC DISPLA THERMAL ELASTIC DISPLA NODE CSFR PFAC 1020) EXPANS CREEP CATION SWELL ATION CEMENT EXPANS DEFORM CREEP CEMENT 10 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 9 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 8 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 7 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 6 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 5 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 4 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 3 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 2 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 1 00000 00000 000 729 000 000 000 1345 2074 734 -407 000 306 CLAD SURFACE COOLANT COOLANT COOLANT CLAD SURFACE CLAD SURFACE HEAT TRANS CLAD OUTER CORROSION NODE TEMP(C) TEMP(C) ENTHALPY(JKG) QUALTY(-) HF(WCM2) COEF(WCM2K) MODE (MICROND) THICKNESS(MIC)
JAEA-DataCode 2013-009
- 190 -
10 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 9 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 8 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 7 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 6 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 5 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 4 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 3 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 2 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 1 2850 2850 125865D+06 -0377(MSUBCOOL) 000000D+00 000000D+00 1 330488D-03 010000 MODE1 SINGLE PHASE FORCED CONVECTION (DITTUS-BOELTER) MODE2 NUCLEATE BOILING (JENS-LOTTES) MODE3 HIGH-FLOW TRANSITION BOILING(MODIFIED CONDIE BENGSTON) MODE4 HIGH-FLOW FILM BOILING(CONDIE BENGSTON) MODE5 LOW-FLOW POST-CHF TRANSITION AND FILM BOILING MODE6 CONDENSATION 0 INITIAL GAS (MOL) = 414D-03 0 FISSION GAS RESULT 0 LOCAL FISSION GAS RELEASE FRACTION (AXIAL NODE) 1 000500 2 000500 3 000500 4 000500 5 000500 6 000500 7 000500 8 000500 9 000500 10 000500 0 ROD AVERAGE FISSION GAS = 000500 FRACTIONS OF GAS MIXTURE (PERCENT) AXIAL NODE RELEASE FRACTION 1 2 3 4 5 6 7 8 9 10 ROD GAS PRESSURE ( MPA ) = 1938 HE 1000 1000 1000 1000 1000 1000 1000 1000 1000 1000 ROD GAS VOLUME ( CM3 ) = 9908 N2 00 00 00 00 00 00 00 00 00 00 (GAPPLENUM)= 2159 7749 KR 00 00 00 00 00 00 00 00 00 00 TOTAL GAS ( MOL ) = 414D-03 XE 00 00 00 00 00 00 00 00 00 00 ROD PRS(MPA) 1938 1938 1938 1938 1938 1938 1938 1938 1938 1938 0 RELEASED IODINE ( GRAMCM2 ) = 274D-24 (AVERAGE) 345D-24 (PEAK) 0 (MOL) HE N2 KR XE TOTAL PRODUCED GAS 130D-24 000D+00 130D-17 870D-17 100E-16 RELEASED GAS 195D-26 000D+00 168D-23 113D-22 130E-22 ROD GAS 414D-03 000D+00 168D-23 113D-22 414E-03 0 RADIAL TEMPERATURE DISTRIBUTION AT AXIAL NODE OF 6 PELLET GAP CLAD 1234567891011 123 285 285 285 285 285 285 285 285 285 285 285 285 285 285 === OPTIONAL OUTPUT (IN ELEMENT AVERAGE) === ---------------------------------------------------------------------------------------------------- | TEMPERATURE DISTRIBUTION IN THE FUEL (DEGC) IWTHE= 1 | ---------------------------------------------------------------------------------------------------- SEG 10 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 9 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 8 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 7 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 6 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 5 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 4 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 3 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 2 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 1 28500 28500 28500 28500 28500 28500 28500 28500 28500 28500 ---------------------------------------------------------------------------------------------------- | RADIUS OF INTRAGRANULAR GAS BUBBLE (ANGSTROM) IWTHE= 4 | ---------------------------------------------------------------------------------------------------- SEG 10 000 000 000 000 000 000 000 000 000 000 9 000 000 000 000 000 000 000 000 000 000 8 000 000 000 000 000 000 000 000 000 000 7 000 000 000 000 000 000 000 000 000 000 6 000 000 000 000 000 000 000 000 000 000 5 000 000 000 000 000 000 000 000 000 000 4 000 000 000 000 000 000 000 000 000 000 3 000 000 000 000 000 000 000 000 000 000 2 000 000 000 000 000 000 000 000 000 000 1 000 000 000 000 000 000 000 000 000 000 ---------------------------------------------------------------------------------------------------- | FISSION GAS RELEASE RATE IN A RING () IWTHE= 14 | ---------------------------------------------------------------------------------------------------- SEG 10 050 050 050 050 050 050 050 050 050 050 9 050 050 050 050 050 050 050 050 050 050 8 050 050 050 050 050 050 050 050 050 050 7 050 050 050 050 050 050 050 050 050 050 6 050 050 050 050 050 050 050 050 050 050 5 050 050 050 050 050 050 050 050 050 050 4 050 050 050 050 050 050 050 050 050 050 3 050 050 050 050 050 050 050 050 050 050 2 050 050 050 050 050 050 050 050 050 050 1 050 050 050 050 050 050 050 050 050 050 ---------------------------------------------------------------------------------------------------- BURNUP DISTRIBUTION IN THE FUEL (MWDT) IWTHE= 18 ---------------------------------------------------------------------------------------------------- SEG 10 00 00 00 00 00 00 00 00 00 00 9 00 00 00 00 00 00 00 00 00 00 8 00 00 00 00 00 00 00 00 00 00 7 00 00 00 00 00 00 00 00 00 00 6 00 00 00 00 00 00 00 00 00 00 5 00 00 00 00 00 00 00 00 00 00 4 00 00 00 00 00 00 00 00 00 00 3 00 00 00 00 00 00 00 00 00 00 2 00 00 00 00 00 00 00 00 00 00 1 00 00 00 00 00 00 00 00 00 00
JAEA-DataCode 2013-009
- 191 -
================================================================================================================================== MECHANICAL ANALYSIS INFORMATION OUTPUT STAGE NUMBER = 1 TIME = 0 H 0 M 0 S 00 MS ROD GAS PRESS(MPA) = 1938 COOLANT PRESS(MPA) = 15400 AXIAL FORCE(N) = -6479344 ================================================================================================================================== ---- ------ -------------------------------------------------- ----------------- -------------------- ------------ SEG LHR B U R N U P FAST NEUTRON FLUX FAST NEUTRON FLUENCE FISSION RATE (WCM) (GJKGU) (MWDTU) (MWDTUO2) (FISSCC) (NCM2SEC) (NCM2) (FISSCCSEC) ---- ------ -------------------------------------------------- ----------------- -------------------- ------------ 10 00 200860D-15 232477D-14 204924D-14 579572D+02 270500D+09 973800D+03 319723D+08 9 00 291823D-15 337758D-14 297727D-14 842040D+02 393000D+09 141480D+04 464514D+08 8 00 345658D-15 400067D-14 352651D-14 997378D+02 465500D+09 167580D+04 550207D+08 7 00 373132D-15 431866D-14 380682D-14 107665D+03 502500D+09 180900D+04 593940D+08 6 00 431794D-15 499761D-14 440530D-14 124592D+03 581500D+09 209340D+04 687315D+08 5 00 441818D-15 511364D-14 450758D-14 127484D+03 595000D+09 214200D+04 703272D+08 4 00 426596D-15 493745D-14 435227D-14 123092D+03 574500D+09 206820D+04 679041D+08 3 00 371276D-15 429717D-14 378788D-14 107130D+03 500000D+09 180000D+04 590985D+08 2 00 321154D-15 371705D-14 327651D-14 926673D+02 432500D+09 155700D+04 511202D+08 1 00 230191D-15 266425D-14 234848D-14 664205D+02 310000D+09 111600D+04 366410D+08 ---------------------------------------------------------------------------------------------------- STRESS(RADIAL) (MPA) IWROD= 1 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 9 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 8 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 7 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 6 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 5 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 4 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 3 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 2 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 1 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 SEGMENT NUM 10 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 9 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 8 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 7 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 6 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 5 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 4 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 3 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 2 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 1 -29 -49 -68 -86 -103 -118 -133 -147 -154 -154 ---------------------------------------------------------------------------------------------------- STRESS(HOOP) (MPA) IWROD= 2 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 9 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 8 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 7 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 6 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 5 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 4 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 3 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 2 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00
JAEA-DataCode 2013-009
- 192 -
1 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 SEGMENT NUM 10 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 9 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 8 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 7 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 6 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 5 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 4 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 3 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 2 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 1 -1017 -997 -979 -961 -944 -928 -914 -899 60 60 ---------------------------------------------------------------------------------------------------- STRESS(AXIAL) (MPA) IWROD= 3 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 9 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 8 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 7 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 6 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 5 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 4 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 3 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 2 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 1 -00 -00 -00 -00 -00 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -01 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 -02 SEGMENT NUM 10 -519 -519 -519 -519 -519 -519 -519 -519 50 50 9 -519 -519 -519 -519 -519 -519 -519 -519 50 50 8 -519 -519 -519 -519 -519 -519 -519 -519 50 50 7 -519 -519 -519 -519 -519 -519 -519 -519 50 50 6 -519 -519 -519 -519 -519 -519 -519 -519 50 50 5 -519 -519 -519 -519 -519 -519 -519 -519 50 50 4 -519 -519 -519 -519 -519 -519 -519 -519 50 50 3 -519 -519 -519 -519 -519 -519 -519 -519 50 50 2 -519 -519 -519 -519 -519 -519 -519 -519 50 50 1 -519 -519 -519 -519 -519 -519 -519 -519 50 50 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(RADIAL) (001) IWROD= 12 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 9 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 8 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 7 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 6 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 5 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 4 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 3 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 2 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 1 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 SEGMENT NUM 10 240 237 234 231 228 225 223 221 -177 -177 9 240 237 234 231 228 225 223 221 -177 -177
JAEA-DataCode 2013-009
- 193 -
8 240 237 234 231 228 225 223 221 -177 -177 7 240 237 234 231 228 225 223 221 -177 -177 6 240 237 234 231 228 225 223 221 -177 -177 5 240 237 234 231 228 225 223 221 -177 -177 4 240 237 234 231 228 225 223 221 -177 -177 3 240 237 234 231 228 225 223 221 -177 -177 2 240 237 234 231 228 225 223 221 -177 -177 1 240 237 234 231 228 225 223 221 -177 -177 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(HOOP) (001) IWROD= 13 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 9 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 8 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 7 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 6 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 5 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 4 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 3 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 2 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 1 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 506 SEGMENT NUM 10 75 79 82 85 88 90 93 95 96 96 9 75 79 82 85 88 90 93 95 96 96 8 75 79 82 85 88 90 93 95 96 96 7 75 79 82 85 88 90 93 95 96 96 6 75 79 82 85 88 90 93 95 96 96 5 75 79 82 85 88 90 93 95 96 96 4 75 79 82 85 88 90 93 95 96 96 3 75 79 82 85 88 90 93 95 96 96 2 75 79 82 85 88 90 93 95 96 96 1 75 79 82 85 88 90 93 95 96 96 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(AXIAL) (001) IWROD= 14 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 9 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 8 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 7 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 6 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 5 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 4 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 3 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 2 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 1 676 676 676 676 676 675 675 675 675 675 675 674 674 674 673 673 672 672 671 670 669 668 668 668 668 668 668 668 668 668 668 668 668 668 668 668 SEGMENT NUM 10 75 75 75 75 75 75 75 75 75 75 9 75 75 75 75 75 75 75 75 75 75 8 75 75 75 75 75 75 75 75 75 75 7 75 75 75 75 75 75 75 75 75 75 6 75 75 75 75 75 75 75 75 75 75 5 75 75 75 75 75 75 75 75 75 75 4 75 75 75 75 75 75 75 75 75 75 3 75 75 75 75 75 75 75 75 75 75
JAEA-DataCode 2013-009
- 194 -
2 75 75 75 75 75 75 75 75 75 75 1 75 75 75 75 75 75 75 75 75 75 --------------------------------------------------------------------------------------------------------------------- DISPLACEMENT OF NODES (MICRON) GAP IWROD=18 --------------------------------------------------------------------------------------------------------------------- (R-DIRECTION OF Pellet) 10 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 9 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 8 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 7 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 6 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 5 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 4 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 3 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 2 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 1 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 (R-DIRECTION OF Cladding) 10 31 33 35 37 39 41 43 45 47 47 47 9 31 33 35 37 39 41 43 45 47 47 47 8 31 33 35 37 39 41 43 45 47 47 47 7 31 33 35 37 39 41 43 45 47 47 47 6 31 33 35 37 39 41 43 45 47 47 47 5 31 33 35 37 39 41 43 45 47 47 47 4 31 33 35 37 39 41 43 45 47 47 47 3 31 33 35 37 39 41 43 45 47 47 47 2 31 33 35 37 39 41 43 45 47 47 47 1 31 33 35 37 39 41 43 45 47 47 47 (Z-DIRECTION) --------- ----------------- ----------------- SEG NUM PELLET CLADDING --------- ----------------- ----------------- 772674 (Plenum) 10 5414193 753509 9 4872774 678158 8 4331355 602807 7 3789935 527456 6 3248516 452105 5 2707097 376754 4 2165677 301403 3 1624258 226053 2 1082839 150702 1 541419 75351 --------------------------------------------------------------------------------------------------------------------- DISPLACEMENT INCREMENT OF NODES (MICRON) GAP IWROD=18 --------------------------------------------------------------------------------------------------------------------- (R-DIRECTION OF Pellet) 10 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 9 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 8 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 7 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 6 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314
JAEA-DataCode 2013-009
- 195 -
5 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 4 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 3 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 2 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 1 00 35 49 60 69 77 85 91 98 104 109 115 120 125 129 134 138 143 147 151 155 158 162 166 169 173 176 180 183 186 189 192 196 199 202 205 207 32314 (R-DIRECTION OF Cladding) 10 31 33 35 37 39 41 43 45 47 47 47 9 31 33 35 37 39 41 43 45 47 47 47 8 31 33 35 37 39 41 43 45 47 47 47 7 31 33 35 37 39 41 43 45 47 47 47 6 31 33 35 37 39 41 43 45 47 47 47 5 31 33 35 37 39 41 43 45 47 47 47 4 31 33 35 37 39 41 43 45 47 47 47 3 31 33 35 37 39 41 43 45 47 47 47 2 31 33 35 37 39 41 43 45 47 47 47 1 31 33 35 37 39 41 43 45 47 47 47 (Z-DIRECTION) --------- ----------------- ----------------- SEG NUM PELLET CLADDING --------- ----------------- ----------------- 772674 (Plenum) 10 5414193 753509 9 4872774 678158 8 4331355 602807 7 3789935 527456 6 3248516 452105 5 2707097 376754 4 2165677 301403 3 1624258 226053 2 1082839 150702 1 541419 75351 STAGE NO 1 PELLET DISPLACEMENT (MICRONS) CLADDING DISPLACEMENT (MICRONS) CLEARANCE CONTACT THERMAL ELASTIC DENSIFI IRRAD RELOC DISPLA THERMAL ELASTIC DISPLA NODE (MICRONS) FORCE(MPA) EXPANS DEFORM CREEP CATION SWELL ATION CEMENT EXPANS DEFORM CREEP CEMENT 10 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 9 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 8 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 7 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 6 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 5 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 4 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 3 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 2 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 1 32314 0000 729 000 000 000 000 1345 2074 734 -407 -000 306 OUTPUT ---STAGE--- 245 IFEM = 6 ---------------------------------------------------------------------------------------------------- |THERMAL ANALYSIS INFORMATION | | STAGE NO 245 | | TIME (HMSMS) 139055442965 | | COOLANT TEMPERATURE 28500 DEGC | | COOLANT PRESSURE 154D+01 MPA | ---------------------------------------------------------------------------------------------------- LHR BURN UP GAP CONDUCTANCE (WCM2-K) TEMPERATURE (C) CLEARANCE CONTACT NODE (WCM) (MWDTU) TOTAL GAS SOLID RAD PC PS CI CO (MICRONS) FORCE(MPA) NODE 10 1664 139916 2202 2198 0000 00043 7375 3823 3532 3253 2311 0000 10 9 2353 200109 4987 3357 0061 00047 9618 3956 3774 3385 0000 8141 9 8 2766 236006 6250 3446 0067 00050 11233 4093 3923 3470 0000 9306 8 7 3076 259181 6921 3494 0068 00053 12522 4205 4033 3534 0000 9540 7 6 3399 292014 7687 3535 0065 00056 14005 4335 4164 3618 0000 9354 6 5 3477 298764 7775 3545 0065 00056 14343 4351 4178 3620 0000 9477 5 4 3375 289333 7481 3503 0062 00054 13823 4281 4107 3562 0000 8991 4 3 3133 261438 6714 3467 0065 00052 12651 4158 3978 3467 0000 9267 3 2 2599 220676 5349 3367 0062 00047 10420 3945 3758 3327 0000 8608 2 1 1884 159197 3062 3050 0004 00042 7860 3727 3490 3172 0000 0576 1 BURN UP PELLET DISPLACEMENT (MICRONS) CLADDING DISPLACEMENT (MICRONS) (FISSCC THERMAL DENSIFI IRRAD RELOC DISPLA THERMAL ELASTIC DISPLA NODE CSFR PFAC 1020) EXPANS CREEP CATION SWELL ATION CEMENT EXPANS DEFORM CREEP CEMENT 10 00000 00000 346 1956 -142 -2035 1123 1244 2128 908 -368 -2965 -2641 9 00000 00000 495 2684 -1053 -2338 1606 1126 1827 970 -113 -3777 -3173 8 00000 00000 584 3300 -1916 -2451 1894 1131 1748 1008 -085 -3905 -3252 7 00000 00000 641 3849 -2657 -2505 2080 1139 1713 1036 -084 -3960 -3287 6 00000 00000 723 4556 -3814 -2564 2344 1140 1471 1070 -093 -4200 -3529 5 00000 00000 739 4726 -4054 -2574 2398 1139 1431 1073 -090 -4243 -3569
JAEA-DataCode 2013-009
- 196 -
4 00000 00000 716 4458 -3697 -2560 2322 1144 1493 1054 -101 -4158 -3507 3 00000 00000 647 3896 -2702 -2510 2098 1142 1740 1020 -090 -3915 -3260 2 00000 00000 546 2967 -1397 -2407 1771 1129 1861 963 -100 -3749 -3139 1 00000 00000 394 2083 -195 -2152 1278 1205 2182 894 -344 -3143 -2818 CLAD SURFACE COOLANT COOLANT COOLANT CLAD SURFACE CLAD SURFACE HEAT TRANS CLAD OUTER CORROSION NODE TEMP(C) TEMP(C) ENTHALPY(JKG) QUALTY(-) HF(WCM2) COEF(WCM2K) MODE (MICROND) THICKNESS(MIC) 10 3215 2968 132152D+06 -0313(MSUBCOOL) 534824D+01 215763D+00 1 180640D-02 658399 9 3310 2959 131682D+06 -0317(MSUBCOOL) 756199D+01 215472D+00 1 300755D-02 941862 8 3361 2948 131084D+06 -0324(MSUBCOOL) 888938D+01 215103D+00 1 412772D-02 1163614 7 3395 2935 130401D+06 -0331(MSUBCOOL) 988361D+01 214685D+00 1 520368D-02 1328893 6 3430 2921 129644D+06 -0338(MSUBCOOL) 109188D+02 214225D+00 1 700957D-02 1626736 5 3428 2906 128841D+06 -0347(MSUBCOOL) 111703D+02 213740D+00 1 705977D-02 1625651 4 3399 2891 128040D+06 -0355(MSUBCOOL) 108430D+02 213260D+00 1 575005D-02 1422411 3 3349 2876 127279D+06 -0363(MSUBCOOL) 100673D+02 212808D+00 1 407496D-02 1104054 2 3257 2863 126609D+06 -0369(MSUBCOOL) 835237D+01 212412D+00 1 240772D-02 791306 1 3139 2853 126085D+06 -0375(MSUBCOOL) 605449D+01 212104D+00 1 130984D-02 517308 0 INITIAL GAS (MOL) = 414D-03 0 FISSION GAS RESULT 0 LOCAL FISSION GAS RELEASE FRACTION (AXIAL NODE) 1 000500 2 000500 3 001515 4 005243 5 007439 6 005951 7 001292 8 000500 9 000500 10 000500 0 ROD AVERAGE FISSION GAS = 002837 FRACTIONS OF GAS MIXTURE (PERCENT) AXIAL NODE RELEASE FRACTION 1 2 3 4 5 6 7 8 9 10 ROD GAS PRESSURE ( MPA ) = 2493 HE 900 900 900 900 900 900 900 900 900 900 ROD GAS VOLUME ( CM3 ) = 9031 N2 00 00 00 00 00 00 00 00 00 00 (GAPPLENUM)= 1326 7705 KR 13 13 13 13 13 13 13 13 13 13 TOTAL GAS ( MOL ) = 432D-03 XE 87 87 87 87 87 87 87 87 87 87 ROD PRS(MPA) 2493 2493 2493 2493 2493 2493 2493 2493 2493 2493 0 RELEASED IODINE ( GRAMCM2 ) = 922D-06 (AVERAGE) 240D-05 (PEAK) 0 (MOL) HE N2 KR XE TOTAL PRODUCED GAS 753D-05 000D+00 200D-03 134D-02 154E-02 RELEASED GAS 187D-06 000D+00 566D-05 379D-04 437E-04 ROD GAS 414D-03 000D+00 566D-05 379D-04 432E-03 0 RADIAL TEMPERATURE DISTRIBUTION AT AXIAL NODE OF 6 PELLET GAP CLAD 1234567891011 123 1401 1389 1357 1302 1227 1133 1022 895 755 605 433 416 388 362 === OPTIONAL OUTPUT (IN ELEMENT AVERAGE) === ---------------------------------------------------------------------------------------------------- | TEMPERATURE DISTRIBUTION IN THE FUEL (DEGC) IWTHE= 1 | ---------------------------------------------------------------------------------------------------- SEG 10 73551 72777 71242 68962 65967 62292 57977 53065 47590 41474 9 95854 94584 92066 88339 83465 77521 70599 62799 54202 44636 8 111919 110298 107088 102339 96136 88588 79831 70009 59245 47287 7 124739 122842 119084 113521 106255 97420 87188 75745 63255 49407 6 139497 137303 132947 126487 118032 107739 95815 82499 68002 51914 5 142861 140598 136102 129431 120693 110052 97723 83958 68981 52362 4 137688 135519 131216 124836 116488 106330 94567 81432 67131 51262 3 126020 124080 120235 114544 107112 98079 87623 75938 63198 49083 2 103833 102368 99465 95171 89561 82732 74800 65889 56103 45226 1 78367 77457 75652 72976 69465 65168 60137 54429 48092 41021 ---------------------------------------------------------------------------------------------------- | RADIUS OF INTRAGRANULAR GAS BUBBLE (ANGSTROM) IWTHE= 4 | ---------------------------------------------------------------------------------------------------- SEG 10 236 236 236 236 237 238 239 241 245 260 9 250 249 245 241 240 241 242 244 248 267 8 429 410 352 292 256 243 242 244 248 269 7 797 762 646 487 341 261 243 243 247 269 6 1141 1136 1073 885 621 371 260 246 249 273 5 1137 1141 1129 978 704 416 269 246 249 273 4 1136 1119 1028 831 575 348 256 245 249 272 3 837 801 680 512 354 263 242 242 246 268 2 297 290 269 251 243 241 242 244 248 268 1 238 238 238 239 239 240 241 243 247 264 ---------------------------------------------------------------------------------------------------- | FISSION GAS RELEASE RATE IN A RING () IWTHE= 14 | ---------------------------------------------------------------------------------------------------- SEG 10 050 050 050 050 050 050 050 050 050 050 9 050 050 050 050 050 050 050 050 050 050 8 050 050 050 050 050 050 050 050 050 050 7 1586 1363 663 090 050 050 050 050 050 050 6 5579 5124 3776 2259 715 050 050 050 050 050 5 6538 6169 4727 2842 1114 061 050 050 050 050 4 4973 4571 3384 2006 502 050 050 050 050 050 3 1866 1630 876 139 050 050 050 050 050 050 2 050 050 050 050 050 050 050 050 050 050 1 050 050 050 050 050 050 050 050 050 050 ---------------------------------------------------------------------------------------------------- BURNUP DISTRIBUTION IN THE FUEL (MWDT) IWTHE= 18 ---------------------------------------------------------------------------------------------------- SEG 10 128403 128525 128726 128963 129226 129511 129822 130159 130515 130887 9 181416 181652 181976 182343 182745 183175 183640 184142 184669 185216 8 212546 212866 213272 213724 214214 214735 215298 215901 216533 217188 7 232465 232844 233307 233817 234366 234948 235574 236245 236946 237672 6 260453 260926 261474 262069 262705 263375 264094 264862 265664 266493 5 266174 266667 267234 267846 268501 269189 269927 270716 271539 272390 4 258177 258642 259183 259771 260400 261062 261773 262534 263327 264148
JAEA-DataCode 2013-009
- 197 -
3 234397 234783 235252 235767 236322 236910 237542 238220 238928 239661 2 199294 199576 199947 200362 200814 201295 201816 202376 202962 203571 1 145500 145656 145894 146171 146477 146807 147167 147556 147966 148393 ================================================================================================================================== MECHANICAL ANALYSIS INFORMATION OUTPUT STAGE NUMBER = 245 TIME = 13905 H 54 M 42 S9651 MS ROD GAS PRESS(MPA) = 2493 COOLANT PRESS(MPA) = 15400 AXIAL FORCE(N) = -6458962 ================================================================================================================================== ---- ------ -------------------------------------------------- ----------------- -------------------- ------------ SEG LHR B U R N U P FAST NEUTRON FLUX FAST NEUTRON FLUENCE FISSION RATE (WCM) (GJKGU) (MWDTU) (MWDTUO2) (FISSCC) (NCM2SEC) (NCM2) (FISSCCSEC) ---- ------ -------------------------------------------------- ----------------- -------------------- ------------ 10 1664 120888D+03 139916D+04 123334D+04 348815D+20 831989D+13 293344D+21 983386D+12 9 2353 172895D+03 200109D+04 176393D+04 498879D+20 117654D+14 420078D+21 139064D+13 8 2766 203909D+03 236006D+04 208035D+04 588370D+20 138323D+14 495608D+21 163493D+13 7 3076 223932D+03 259181D+04 228463D+04 646146D+20 153807D+14 543515D+21 181795D+13 6 3399 252300D+03 292014D+04 257405D+04 728000D+20 169942D+14 613706D+21 200867D+13 5 3477 258132D+03 298764D+04 263355D+04 744827D+20 173857D+14 627896D+21 205494D+13 4 3375 249984D+03 289333D+04 255042D+04 721315D+20 168744D+14 607926D+21 199451D+13 3 3133 225883D+03 261438D+04 230453D+04 651773D+20 156647D+14 547649D+21 185152D+13 2 2599 190664D+03 220676D+04 194522D+04 550153D+20 129941D+14 463175D+21 153587D+13 1 1884 137546D+03 159197D+04 140329D+04 396883D+20 941785D+13 333962D+21 111316D+13 ---------------------------------------------------------------------------------------------------- STRESS(RADIAL) (MPA) IWROD= 1 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 -11 -11 -10 -10 -10 -10 -09 -09 -09 -08 -08 -08 -07 -07 -07 -06 -06 -06 -05 -05 -05 -05 -04 -04 -04 -03 -03 -03 -03 -02 -02 -02 -01 -01 -01 -00 9 -84 -84 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -84 -84 -85 -85 -85 -85 -85 -85 -85 -85 -85 -84 -84 -83 -83 8 -83 -84 -84 -84 -84 -84 -84 -85 -85 -85 -85 -85 -85 -85 -85 -85 -85 -85 -86 -86 -87 -88 -89 -90 -90 -91 -92 -92 -92 -93 -93 -93 -94 -94 -94 -94 7 -57 -59 -62 -65 -68 -70 -72 -74 -75 -76 -77 -77 -78 -79 -79 -80 -81 -82 -83 -84 -86 -87 -88 -89 -90 -91 -92 -92 -93 -94 -94 -95 -95 -95 -96 -96 6 -67 -67 -67 -67 -67 -66 -65 -65 -65 -66 -67 -69 -70 -72 -74 -75 -77 -78 -79 -81 -82 -83 -84 -85 -86 -87 -88 -88 -89 -90 -91 -91 -92 -93 -93 -94 5 -71 -71 -71 -71 -72 -72 -72 -71 -71 -72 -73 -74 -75 -77 -78 -80 -81 -82 -83 -84 -85 -86 -87 -88 -88 -89 -90 -90 -91 -92 -92 -93 -93 -94 -95 -95 4 -58 -58 -58 -58 -56 -55 -55 -56 -58 -59 -61 -62 -64 -65 -67 -69 -71 -72 -74 -75 -76 -78 -79 -80 -81 -82 -83 -84 -85 -86 -87 -87 -88 -89 -90 -90 3 -50 -52 -56 -59 -63 -65 -68 -69 -71 -72 -73 -74 -75 -76 -76 -77 -78 -79 -80 -81 -83 -84 -85 -86 -87 -88 -89 -89 -90 -91 -91 -92 -92 -93 -93 -93 2 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -83 -84 -85 -86 -86 -87 -87 -87 -88 -88 -88 -88 -88 -88 -88 -88 -87 1 -20 -20 -19 -19 -19 -18 -18 -18 -17 -17 -17 -16 -16 -15 -15 -14 -14 -13 -13 -12 -12 -12 -11 -11 -11 -10 -10 -09 -09 -09 -08 -08 -07 -07 -06 -06 SEGMENT NUM 10 -34 -49 -64 -78 -93 -107 -120 -141 -154 -154 9 -108 -114 -119 -125 -130 -135 -141 -149 -154 -154 8 -119 -123 -127 -132 -136 -140 -144 -150 -154 -154 7 -121 -125 -129 -133 -137 -141 -144 -150 -154 -154 6 -120 -124 -127 -131 -135 -139 -144 -150 -154 -154 5 -121 -125 -128 -132 -136 -140 -144 -150 -154 -154 4 -116 -121 -125 -129 -133 -138 -143 -149 -154 -154 3 -119 -123 -127 -131 -135 -139 -144 -150 -154 -154 2 -113 -118 -122 -127 -132 -137 -142 -149 -154 -154 1 -39 -53 -67 -81 -94 -108 -121 -141 -154 -154 ---------------------------------------------------------------------------------------------------- STRESS(HOOP) (MPA) IWROD= 2 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 -11 -10 -09 -08 -08 -07 -06 -05 -04 -03 -02 -01 00 01 02 03 04 05 06 07 06 06 08 09 11 12 13 15 16 17 18 20 21 22 23 25 9 -84 -84 -84 -84 -84 -84 -84 -85 -85 -85 -86 -86 -86 -87 -87 -88 -88 -89 -89 -100 -108 -107 -104 -101 -98 -94 -91 -87 -83 -78 -72 -64 -56 -47 -37 -27 8 -83 -85 -86 -87 -87 -87 -88 -88 -88 -88 -89 -89 -90 -90 -91 -92 -93 -102 -117 -124 -127 -128 -126 -125 -123 -121 -119 -117 -114 -111 -109 -108 -107 -105 -102 -97 7 -57 -69 -80 -87 -91 -94 -95 -96 -96 -96 -96 -97 -97 -97 -98 -109 -124 -132 -136 -137 -138 -138 -137 -136 -135 -134 -133 -131 -129 -127 -125 -122 -121 -122 -122 -122 6 -67 -67 -68 -69 -62 -50 -61 -73 -83 -89 -94 -105 -116 -123 -127 -128 -129 -130 -130 -130 -131 -131 -131 -131 -131 -131 -132 -132 -133 -133 -134 -135 -135 -138 -142 -148 5 -71 -72 -72 -74 -75 -77 -68 -66 -77 -88 -100 -111 -118 -122 -124 -125 -125 -125 -125 -126 -126 -126 -126 -125 -125 -126 -126 -126 -127 -128 -129 -130 -132 -135 -139 -145 4 -58 -59 -59 -51 -42 -53 -66 -78 -86 -91 -94 -96 -105 -117 -124 -128 -129 -130 -131 -132 -132 -133 -133 -133 -133 -133 -133 -134 -134 -135 -135 -135 -136 -139 -144 -150 3 -50 -63 -75 -85 -91 -94 -96 -96 -97 -97 -97 -97 -97 -97 -98 -103 -119 -129 -133 -135 -136 -136 -135 -134
JAEA-DataCode 2013-009
- 198 -
-133 -131 -130 -128 -126 -124 -121 -120 -120 -121 -121 -121 2 -83 -84 -84 -84 -84 -84 -85 -85 -85 -86 -86 -86 -87 -87 -88 -89 -89 -90 -96 -112 -118 -118 -116 -113 -111 -108 -104 -101 -98 -95 -91 -86 -80 -72 -62 -50 1 -20 -19 -18 -17 -16 -15 -14 -13 -11 -10 -08 -06 -04 -03 -01 -00 01 02 03 04 02 03 04 06 08 09 11 12 14 16 17 19 20 22 23 25 SEGMENT NUM 10 -854 -872 -891 -910 -929 -947 -966 -978 -164 -165 9 -399 -410 -422 -434 -446 -460 -473 -484 -157 -157 8 -341 -349 -358 -368 -378 -388 -399 -407 -157 -157 7 -328 -337 -346 -355 -364 -374 -384 -392 -157 -157 6 -328 -339 -351 -363 -376 -389 -403 -415 -157 -157 5 -321 -331 -343 -355 -368 -382 -396 -408 -157 -157 4 -345 -357 -370 -383 -397 -412 -427 -440 -157 -158 3 -339 -349 -359 -369 -380 -391 -403 -412 -157 -157 2 -370 -381 -393 -405 -418 -432 -446 -458 -157 -157 1 -796 -820 -845 -870 -895 -919 -944 -963 -163 -163 ---------------------------------------------------------------------------------------------------- STRESS(AXIAL) (MPA) IWROD= 3 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 00 00 00 00 00 00 00 00 -10 -11 -10 -09 -08 -06 -05 -04 -03 -02 -00 00 01 02 03 04 9 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -29 -44 -43 -37 -30 -23 -17 -10 -04 00 03 06 09 12 15 18 21 8 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -27 -56 -67 -71 -71 -67 -63 -58 -52 -45 -37 -28 -18 -08 -00 04 09 14 19 7 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -31 -60 -73 -78 -81 -82 -81 -78 -74 -70 -65 -60 -53 -46 -37 -27 -15 -03 03 10 16 6 -64 -64 -64 -62 -48 -00 -00 -00 -00 -00 -07 -30 -49 -60 -66 -69 -70 -70 -70 -70 -69 -68 -65 -62 -58 -54 -50 -45 -40 -34 -27 -18 -08 01 09 17 5 -69 -69 -69 -69 -68 -64 -43 -12 -08 -18 -33 -46 -56 -61 -64 -65 -65 -64 -64 -62 -61 -59 -56 -52 -49 -45 -40 -35 -30 -24 -18 -10 -02 05 13 21 4 -56 -55 -54 -38 -00 -00 -00 -00 -00 -00 -00 -03 -27 -48 -60 -65 -68 -69 -70 -70 -69 -68 -65 -62 -59 -55 -50 -45 -40 -33 -25 -15 -04 04 11 19 3 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -17 -50 -66 -73 -76 -77 -76 -72 -68 -64 -58 -52 -45 -37 -27 -15 -04 03 09 16 22 2 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -20 -51 -61 -61 -56 -50 -43 -35 -27 -19 -10 -03 02 05 09 13 17 20 1 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -08 -28 -32 -31 -29 -28 -26 -24 -23 -21 -19 -17 -15 -12 -10 -08 -06 SEGMENT NUM 10 -442 -458 -475 -491 -507 -522 -538 -553 -159 -159 9 -428 -445 -462 -480 -498 -517 -537 -556 -159 -159 8 -394 -410 -427 -445 -463 -482 -503 -523 -158 -159 7 -367 -383 -399 -417 -436 -455 -475 -496 -158 -158 6 -333 -348 -365 -383 -401 -421 -443 -465 -158 -158 5 -327 -343 -359 -377 -396 -416 -437 -459 -158 -158 4 -342 -359 -377 -396 -416 -437 -460 -484 -158 -158 3 -372 -389 -407 -427 -447 -468 -490 -513 -158 -158 2 -406 -424 -442 -461 -481 -502 -523 -545 -158 -159 1 -411 -430 -448 -467 -485 -503 -521 -539 -159 -159 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(RADIAL) (001) IWROD= 12 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 631 617 605 593 582 571 560 549 539 529 520 511 502 493 484 476 467 459 451 443 453 447 436 425 415 405 396 387 379 370 363 355 348 341 334 328 9 586 569 554 539 525 511 498 485 472 460 448 436 424 413 402 391 381 370 360 368 410 395 367 343 320 300 282 266 252 240 228 218 208 200 192 185 8 526 515 503 491 478 465 452 440 429 418 408 398 389 380 371 363 355 359 408 492 556 531 482 437 395 356 321 290 262 239 220 205 192 179 168 157 7 327 449 490 500 494 482 467 451 436 422 409 397 386 376 367 374 416 484 569 662 722 685 618 555 497 443 393 347 306 269 238 213 195 180 167 154 6 -235 -39 97 183 288 499 605 628 616 591 564 554 566 593 633 687 748 815 889 970 1010 950 858 772 691 616 546 481 420 365 316 274 240 217 200 183 5 -346 -85 97 232 325 403 490 583 614 612 607 613 629 657 697 747 804 866 937 1013 1050 986 889 798 713 635 562 493 431 373 322 279 244 222 203 187 4 -192 -24 73 188 475 624 663 654 627 596 566 538 527 544 579 628 689 758 832 915 960 902 813 729 651 578 511 449 392 340 295 257 229 210 194 178 3 309 471 526 539 534 520 502 484 466 450 435 421 408 397 386 382 412 471 552 643 700 662 595 532 474 420 371 326 286 252 225 205 189 175 162 150 2 595 576 560 545 530 515 501 487 474 462 449 438 426 415 404 394 383 373 370 416 470 450 412 378 346 318 293 271 253 237 223 210 199 189 180 172 1 667 650 635 621 607 594 580 567 555 543 531 520 510 499 489 479 469 460 450 442 457 450 436 423
JAEA-DataCode 2013-009
- 199 -
410 398 387 376 365 355 345 336 327 318 310 301 SEGMENT NUM 10 1033 993 958 924 892 862 833 796 -187 -187 9 1293 1245 1201 1160 1121 1083 1047 1002 -19 -19 8 1404 1352 1305 1261 1218 1178 1139 1090 50 51 7 1475 1421 1372 1325 1280 1238 1197 1146 92 93 6 1612 1553 1500 1449 1400 1354 1310 1254 183 184 5 1633 1573 1519 1467 1418 1371 1327 1270 198 199 4 1586 1528 1475 1424 1376 1330 1287 1232 171 172 3 1453 1398 1349 1303 1259 1216 1176 1125 84 84 2 1299 1250 1206 1163 1123 1085 1048 1002 -09 -09 1 1071 1029 992 956 921 889 858 819 -150 -151 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(HOOP) (001) IWROD= 13 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 631 628 625 621 617 613 609 605 602 598 594 591 587 584 581 577 574 571 568 565 562 559 556 554 551 548 545 543 540 537 534 531 529 526 523 520 9 586 583 578 573 569 564 559 554 550 545 541 536 532 528 523 519 515 511 507 503 501 498 496 493 489 486 482 478 474 470 467 463 459 455 451 447 8 526 524 521 517 513 509 505 501 497 493 489 485 482 478 474 471 467 464 462 462 463 465 466 466 465 463 461 458 455 451 447 444 440 436 432 428 7 327 348 375 394 406 414 419 422 423 423 423 422 421 419 418 416 416 417 420 425 431 438 442 446 447 448 447 446 444 441 438 434 431 427 423 420 6 -235 -201 -150 -105 -65 -21 24 65 99 127 149 167 183 198 213 227 242 258 274 291 308 324 337 348 356 361 366 368 370 370 370 369 367 365 362 360 5 -346 -301 -233 -171 -118 -72 -30 09 45 75 101 124 144 163 181 199 217 235 253 272 290 308 322 333 342 348 353 356 358 359 359 358 356 354 352 350 4 -192 -163 -121 -82 -34 22 72 112 144 170 190 206 219 231 243 255 267 280 294 309 325 339 351 360 367 372 375 377 378 377 376 375 373 370 368 365 3 309 336 373 398 415 425 432 436 439 440 440 440 439 437 436 434 433 433 435 439 445 451 455 457 458 458 456 455 452 449 445 442 438 434 430 426 2 595 592 586 581 576 571 566 561 556 551 547 542 538 533 529 525 520 516 512 509 508 506 505 502 499 496 493 489 485 481 476 472 468 464 460 456 1 667 664 659 654 650 645 640 636 631 627 622 618 614 610 606 602 598 594 590 586 583 580 577 574 570 567 564 561 557 554 550 547 544 540 537 534 SEGMENT NUM 10 -619 -588 -560 -533 -509 -485 -463 -433 -415 -414 9 -743 -704 -670 -638 -607 -579 -551 -514 -491 -491 8 -761 -719 -683 -649 -617 -586 -557 -518 -493 -493 7 -768 -726 -688 -653 -619 -588 -558 -517 -492 -491 6 -825 -778 -738 -699 -663 -629 -596 -552 -524 -524 5 -834 -787 -746 -707 -670 -635 -603 -558 -530 -529 4 -820 -774 -734 -696 -660 -626 -594 -551 -523 -523 3 -762 -720 -683 -648 -615 -584 -554 -514 -489 -489 2 -735 -696 -662 -630 -599 -571 -544 -507 -484 -484 1 -661 -628 -599 -571 -545 -521 -498 -466 -447 -447 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(AXIAL) (001) IWROD= 14 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 947 928 909 890 872 855 838 821 805 790 775 761 747 734 721 708 696 684 672 660 590 572 569 566 564 561 558 556 554 551 549 547 545 543 541 538 9 1884 1830 1778 1726 1676 1627 1579 1532 1486 1441 1398 1355 1313 1273 1233 1194 1156 1119 1083 960 845 817 811 806 800 795 790 786 782 777 773 769 765 760 756 751 8 2858 2759 2667 2580 2495 2414 2335 2259 2184 2111 2040 1971 1904 1838 1774 1712 1651 1517 1360 1191 1049 1009 1002 995 988 980 972 964 955 947 940 933 926 920 912 904 7 4034 3742 3528 3360 3219 3094 2979 2872 2769 2671 2575 2483 2393 2306 2220 2051 1881 1708 1527 1339 1184 1139 1133 1126 1119 1111 1103 1094 1084 1074 1063 1053 1044 1035 1026 1015 6 5631 5384 5130 4891 4634 4328 4015 3791 3615 3465 3303 3113 2926 2742 2556 2365 2172 1977 1778 1575 1412 1363 1358 1352 1345 1338 1330 1322 1312 1302 1290 1277 1263 1251 1239 1225 5 5743 5499 5255 5006 4762 4512 4264 4024 3804 3599 3402 3209 3020 2832 2640 2446 2250 2052 1851 1647 1483 1434 1428 1422 1416 1409 1401 1392 1383 1372 1359 1346 1332 1320 1307 1291 4 5598 5340 5098 4838 4437 4071 3820 3632 3475 3337 3209 3077 2892 2709 2527 2343 2153 1960 1764 1563 1401 1354 1348 1341 1335 1327 1319 1310 1300 1288 1276 1263 1250 1239 1226 1210 3 4159 3816 3573 3389 3238 3107 2988 2878 2773 2673 2576 2482 2390 2301 2215 2079 1907 1736 1557 1371 1217 1173 1166 1159 1152 1143 1134 1125 1114 1103 1093 1084 1075 1065 1055 1042 2 2286 2215 2146 2079 2014 1951 1889 1829 1770 1713 1657 1602 1549 1497 1447 1397 1349 1303 1200 1050 920 886 880 873 866 860 853 846 841 835 830 825 820 814 808 802 1 1044 1019 995 972 949 927 906 885 864 845 826 808 791 774 758 742 727 712 697 654 558 537 534 531 528 526 523 520 517 514 511 508 506 503 500 497 SEGMENT NUM 10 352 352 352 352 352 352 352 352 352 352 9 317 317 317 317 317 317 317 317 317 317 8 276 276 276 276 276 276 276 276 276 276 7 247 247 247 247 247 247 247 247 247 247
JAEA-DataCode 2013-009
- 200 -
6 210 210 210 210 210 210 210 210 210 210 5 205 205 205 205 205 205 205 205 205 205 4 219 219 219 219 219 219 219 219 219 219 3 255 255 255 255 255 255 255 255 255 255 2 317 317 317 317 317 317 317 317 317 317 1 368 368 368 368 368 368 368 368 368 368 --------------------------------------------------------------------------------------------------------------------- DISPLACEMENT OF NODES (MICRON) GAP IWROD=18 --------------------------------------------------------------------------------------------------------------------- (R-DIRECTION OF Pellet) 10 -00 43 61 74 85 94 102 110 117 123 129 134 139 144 149 153 157 161 165 169 172 175 179 182 185 188 191 193 196 198 200 203 205 207 209 211 213 2311 9 -00 40 56 68 78 87 94 101 107 112 117 122 126 131 134 138 141 145 148 150 153 156 159 162 164 167 169 171 172 174 175 177 178 179 181 182 183 -0000 8 -00 36 50 61 70 78 85 91 96 101 106 110 114 118 122 125 128 131 134 137 141 145 149 153 156 159 161 163 165 167 168 170 171 172 173 174 175 0000 7 00 22 35 46 55 63 70 76 82 87 91 96 100 104 107 110 114 117 121 126 131 136 141 146 150 153 156 159 161 163 164 166 167 168 169 170 171 0000 6 00 -16 -17 -15 -12 -07 00 08 16 23 30 36 41 47 52 58 64 70 77 84 92 99 106 112 118 123 127 130 134 136 139 140 142 144 145 146 147 0000 5 00 -24 -26 -24 -20 -14 -09 -02 05 12 19 26 32 38 44 50 57 64 71 78 86 94 101 107 113 118 122 126 129 132 134 136 138 140 141 142 143 -0000 4 -00 -13 -14 -12 -09 -01 08 17 25 32 39 45 50 56 61 66 71 77 83 90 97 104 111 117 122 126 130 134 136 139 141 143 145 146 147 148 149 -0000 3 00 21 34 46 56 64 72 79 85 90 95 100 104 108 112 115 118 122 126 130 135 140 145 149 153 156 159 162 164 166 167 169 170 171 172 173 174 0000 2 -00 41 57 69 79 88 95 102 108 114 119 123 128 132 136 139 143 146 149 152 155 159 162 165 168 170 172 174 176 178 179 180 182 183 184 185 186 -0000 1 -00 46 64 78 89 99 108 115 122 129 135 141 146 151 155 160 164 168 172 175 179 182 185 189 192 194 197 200 202 204 207 209 211 213 215 216 218 0000 (R-DIRECTION OF Cladding) 10 -264 -255 -362 -469 -576 -684 -791 -899 -243 -211 -178 9 -317 -306 -413 -521 -628 -736 -845 -953 -298 -252 -205 8 -325 -313 -421 -529 -638 -747 -857 -967 -314 -256 -198 7 -329 -316 -425 -534 -644 -754 -864 -975 -324 -258 -192 6 -353 -339 -449 -560 -671 -782 -894 -1007 -359 -278 -197 5 -357 -343 -453 -563 -674 -786 -897 -1009 -361 -281 -200 4 -351 -337 -446 -555 -665 -775 -885 -996 -345 -274 -204 3 -326 -313 -421 -528 -636 -745 -853 -962 -308 -253 -199 2 -314 -303 -408 -515 -621 -728 -835 -943 -285 -246 -207 1 -282 -272 -378 -483 -589 -695 -802 -909 -249 -224 -199 (Z-DIRECTION) --------- ----------------- ----------------- SEG NUM PELLET CLADDING --------- ----------------- ----------------- 2904804 (Plenum) 10 8359666 2766703 9 7936580 2414740 8 7279799 2097697 7 6464730 1821543 6 5538076 1574351 5 4402830 1364513 4 3197476 1159485 3 2066647 940601 2 1099513 685300 1 386120 368351 --------------------------------------------------------------------------------------------------------------------- DISPLACEMENT INCREMENT OF NODES (MICRON) GAP IWROD=18 --------------------------------------------------------------------------------------------------------------------- (R-DIRECTION OF Pellet) 10 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 2311 9 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -0000 8 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 7 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000
JAEA-DataCode 2013-009
- 201 -
6 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 5 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -0000 4 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -0000 3 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 2 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -0000 1 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 (R-DIRECTION OF Cladding) 10 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 9 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 8 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 7 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 6 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 5 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 4 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 3 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 2 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 1 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 (Z-DIRECTION) --------- ----------------- ----------------- SEG NUM PELLET CLADDING --------- ----------------- ----------------- -0433 (Plenum) 10 -0495 -0495 9 -0503 -0503 8 -0496 -0496 7 -0468 -0468 6 -0421 -0421 5 -0302 -0302 4 -0161 -0161 3 -0059 -0059 2 -0018 -0018 1 -0003 -0003 STAGE NO 245 PELLET DISPLACEMENT (MICRONS) CLADDING DISPLACEMENT (MICRONS) CLEARANCE CONTACT THERMAL ELASTIC DENSIFI IRRAD RELOC DISPLA THERMAL ELASTIC DISPLA NODE (MICRONS) FORCE(MPA) EXPANS DEFORM CREEP CATION SWELL ATION CEMENT EXPANS DEFORM CREEP CEMENT 10 2311 0000 1956 -017 -143 -2035 1123 1244 2128 908 -368 -2978 -2641 9 -0000 8141 2684 -185 -1065 -2338 1606 1126 1827 970 -113 -3780 -3173 8 -0000 9306 3300 -191 -1934 -2451 1894 1131 1748 1008 -085 -3908 -3252 7 0000 9540 3849 -165 -2685 -2505 2080 1139 1713 1036 -084 -3963 -3287 6 0000 9354 4556 -163 -3842 -2564 2344 1140 1471 1070 -093 -4207 -3529 5 -0000 9477 4726 -173 -4085 -2574 2398 1139 1431 1073 -090 -4250 -3569 4 -0000 8991 4458 -147 -3724 -2560 2322 1144 1493 1054 -101 -4165 -3507 3 0000 9267 3896 -155 -2732 -2510 2098 1142 1740 1020 -090 -3919 -3260 2 -0000 8608 2967 -186 -1413 -2407 1771 1129 1861 963 -100 -3752 -3139 1 -0000 0576 2083 -034 -197 -2152 1278 1205 2182 894 -344 -3156 -2818
OUTPUT ---STAGE--- 314 to 530 are skipped OUTPUT ---STAGE--- 618 IFEM = 6 ---------------------------------------------------------------------------------------------------- |THERMAL ANALYSIS INFORMATION | | STAGE NO 618 | | TIME (HMSMS) 3638551 9574 | | COOLANT TEMPERATURE 28500 DEGC | | COOLANT PRESSURE 154D+01 MPA | ---------------------------------------------------------------------------------------------------- LHR BURN UP GAP CONDUCTANCE (WCM2-K) TEMPERATURE (C) CLEARANCE CONTACT NODE (WCM) (MWDTU) TOTAL GAS SOLID RAD PC PS CI CO (MICRONS) FORCE(MPA) NODE 10 779 367727 9573 1237 0033 00034 5022 3225 3194 3062 0000 5971 10 9 1003 503959 9542 1242 0022 00036 5969 3344 3304 3136 0000 4827 9 8 1135 585050 9534 1246 0017 00038 6610 3429 3383 3196 0000 4043 8 7 1195 635879 9531 1250 0014 00039 6963 3480 3432 3237 0000 3668 7 6 1214 687736 9529 1252 0012 00040 7203 3530 3480 3285 0000 3223 6 5 1234 702118 9528 1255 0012 00040 7311 3537 3487 3288 0000 3360 5 4 1241 688741 9524 1254 0014 00039 7257 3499 3449 3247 0000 3799 4 3 1214 645320 9521 1249 0016 00038 6996 3436 3387 3186 0000 4222 3 2 1102 555299 9526 1245 0022 00036 6345 3338 3293 3108 0000 5156 2 1 878 416184 9550 1240 0033 00034 5329 3212 3177 3028 0000 6422 1 BURN UP PELLET DISPLACEMENT (MICRONS) CLADDING DISPLACEMENT (MICRONS)
JAEA-DataCode 2013-009
- 202 -
(FISSCC THERMAL DENSIFI IRRAD RELOC DISPLA THERMAL ELASTIC DISPLA NODE CSFR PFAC 1020) EXPANS CREEP CATION SWELL ATION CEMENT EXPANS DEFORM CREEP CEMENT 10 00000 00000 910 1265 -869 -2648 2827 1164 1650 822 -138 -3787 -3350 9 00000 00000 1247 1528 -2705 -2707 3813 1186 1051 851 -177 -4320 -3949 8 00000 00000 1448 1719 -3904 -2720 4356 1204 609 872 -204 -4716 -4391 7 00000 00000 1573 1830 -4700 -2725 4659 1217 246 885 -220 -5048 -4754 6 00000 00000 1702 1911 -5595 -2728 4910 1234 -292 899 -240 -5541 -5292 5 00000 00000 1737 1945 -5704 -2728 4973 1230 -311 900 -239 -5562 -5311 4 00000 00000 1704 1923 -5328 -2728 4914 1216 -036 889 -224 -5312 -5036 3 00000 00000 1597 1835 -4579 -2725 4710 1211 413 872 -206 -4898 -4587 2 00000 00000 1374 1632 -3115 -2717 4163 1187 1091 847 -171 -4285 -3909 1 00000 00000 1030 1342 -1189 -2678 3185 1164 1733 817 -122 -3719 -3267 CLAD SURFACE COOLANT COOLANT COOLANT CLAD SURFACE CLAD SURFACE HEAT TRANS CLAD OUTER CORROSION NODE TEMP(C) TEMP(C) ENTHALPY(JKG) QUALTY(-) HF(WCM2) COEF(WCM2K) MODE (MICROND) THICKNESS(MIC) 10 3014 2897 128360D+06 -0351(MSUBCOOL) 250161D+01 213451D+00 1 832580D-03 1816573 9 3044 2893 128150D+06 -0354(MSUBCOOL) 322089D+01 213326D+00 1 113146D-02 2701414 8 3059 2888 127899D+06 -0356(MSUBCOOL) 364308D+01 213176D+00 1 144000D-02 3534076 7 3063 2883 127625D+06 -0359(MSUBCOOL) 383222D+01 213013D+00 1 169268D-02 4261788 6 3060 2877 127342D+06 -0362(MSUBCOOL) 389336D+01 212845D+00 1 204166D-02 5404631 5 3058 2872 127054D+06 -0365(MSUBCOOL) 395675D+01 212674D+00 1 206684D-02 5447848 4 3054 2866 126763D+06 -0368(MSUBCOOL) 397981D+01 212502D+00 1 176148D-02 4552731 3 3044 2861 126474D+06 -0371(MSUBCOOL) 389750D+01 212332D+00 1 138437D-02 3411536 2 3023 2856 126202D+06 -0374(MSUBCOOL) 353955D+01 212172D+00 1 100819D-02 2274658 1 2984 2851 125969D+06 -0376(MSUBCOOL) 282018D+01 212036D+00 1 719173D-03 1438407 0 INITIAL GAS (MOL) = 414D-03 0 FISSION GAS RESULT 0 LOCAL FISSION GAS RELEASE FRACTION (AXIAL NODE) 1 001306 2 004371 3 009150 4 012529 5 014209 6 012980 7 008746 8 004846 9 002029 10 000517 0 ROD AVERAGE FISSION GAS = 007950 FRACTIONS OF GAS MIXTURE (PERCENT) AXIAL NODE RELEASE FRACTION 1 2 3 4 5 6 7 8 9 10 ROD GAS PRESSURE ( MPA ) = 3869 HE 555 555 555 555 555 555 555 555 555 555 ROD GAS VOLUME ( CM3 ) = 8502 N2 00 00 00 00 00 00 00 00 00 00 (GAPPLENUM)= 1295 7207 KR 58 58 58 58 58 58 58 58 58 58 TOTAL GAS ( MOL ) = 655D-03 XE 387 387 387 387 387 387 387 387 387 387 ROD PRS(MPA) 3869 3869 3869 3869 3869 3869 3869 3869 3869 3869 0 RELEASED IODINE ( GRAMCM2 ) = 635D-05 (AVERAGE) 123D-04 (PEAK) 0 (MOL) HE N2 KR XE TOTAL PRODUCED GAS 374D-04 000D+00 490D-03 328D-02 381E-02 RELEASED GAS 462D-05 000D+00 390D-04 261D-03 304E-03 ROD GAS 418D-03 000D+00 390D-04 261D-03 655E-03 0 RADIAL TEMPERATURE DISTRIBUTION AT AXIAL NODE OF 6 PELLET GAP CLAD 1234567891011 123 720 717 707 690 666 635 598 553 501 440 353 348 338 328 === OPTIONAL OUTPUT (IN ELEMENT AVERAGE) === ---------------------------------------------------------------------------------------------------- | TEMPERATURE DISTRIBUTION IN THE FUEL (DEGC) IWTHE= 1 | ---------------------------------------------------------------------------------------------------- SEG 10 50137 49790 49097 48058 46674 44945 42870 40441 37627 34186 9 59563 59065 58068 56574 54584 52096 49108 45604 41527 36389 8 65952 65354 64158 62365 59974 56985 53392 49173 44250 37944 7 69470 68820 67520 65570 62969 59716 55803 51201 45821 38860 6 71864 71185 69827 67788 65067 61660 57557 52723 47055 39644 5 72934 72237 70844 68753 65962 62467 58257 53296 47476 39848 4 72394 71698 70308 68220 65434 61948 57749 52805 47010 39435 3 69794 69130 67803 65812 63156 59835 55838 51139 45643 38518 2 63308 62740 61605 59902 57634 54798 51392 47394 42735 36803 1 53189 52782 51969 50751 49129 47102 44670 41821 38518 34434 ---------------------------------------------------------------------------------------------------- | RADIUS OF INTRAGRANULAR GAS BUBBLE (ANGSTROM) IWTHE= 4 | ---------------------------------------------------------------------------------------------------- SEG 10 345 345 345 346 347 349 351 355 362 399 9 389 389 389 390 391 393 396 400 409 457 8 411 411 412 413 414 416 419 424 434 488 7 402 404 414 423 427 429 432 437 448 506 6 367 371 386 407 429 442 445 451 462 523 5 362 365 378 401 427 444 449 454 466 528 4 374 378 392 412 432 442 445 451 462 523 3 400 403 413 424 429 432 435 440 451 509 2 403 403 404 405 406 408 411 415 425 477 1 361 362 362 363 364 366 368 372 380 421 ---------------------------------------------------------------------------------------------------- | FISSION GAS RELEASE RATE IN A RING () IWTHE= 14 | ---------------------------------------------------------------------------------------------------- SEG 10 050 050 050 050 050 050 050 050 050 055 9 050 050 050 050 050 050 050 050 050 483 8 050 050 050 050 050 050 050 050 050 1382 7 1312 1165 685 165 050 050 050 050 050 2533 6 3549 3378 2746 1748 643 053 050 050 050 2856 5 3896 3771 3233 2209 953 092 050 050 050 2949 4 3282 3099 2459 1509 493 050 050 050 050 2863 3 1513 1360 856 247 050 050 050 050 050 2591 2 050 050 050 050 050 050 050 050 050 1261 1 050 050 050 050 050 050 050 050 050 301 ---------------------------------------------------------------------------------------------------- BURNUP DISTRIBUTION IN THE FUEL (MWDT) IWTHE= 18 ----------------------------------------------------------------------------------------------------
JAEA-DataCode 2013-009
- 203 -
SEG 10 324005 324729 325496 326304 327154 328039 328982 329986 331030 332107 9 434959 436249 437487 438743 440035 441356 442749 444225 445754 447329 8 499245 500925 502484 504043 505632 507245 508938 510728 512579 514487 7 538963 540903 542676 544438 546226 548035 549928 551928 553995 556126 6 579130 581344 583344 585321 587320 589338 591444 593669 595967 598336 5 590217 592509 594573 596611 598670 600747 602914 605203 607566 610003 4 579907 582127 584131 586112 588116 590137 592248 594477 596779 599153 3 546300 548289 550103 551904 553729 555576 557507 559547 561656 563829 2 475797 477330 478768 480212 481690 483193 484772 486445 488174 489956 1 363908 364819 365744 366702 367702 368735 369831 370996 372205 373452 ================================================================================================================================== MECHANICAL ANALYSIS INFORMATION OUTPUT STAGE NUMBER = 618 TIME = 36385 H 51 M 9 S5743 MS ROD GAS PRESS(MPA) = 3869 COOLANT PRESS(MPA) = 15400 AXIAL FORCE(N) = -8371215 ================================================================================================================================== ---- ------ -------------------------------------------------- ----------------- -------------------- ------------ SEG LHR B U R N U P FAST NEUTRON FLUX FAST NEUTRON FLUENCE FISSION RATE (WCM) (GJKGU) (MWDTU) (MWDTUO2) (FISSCC) (NCM2SEC) (NCM2) (FISSCCSEC) ---- ------ -------------------------------------------------- ----------------- -------------------- ------------ 10 779 317716D+03 367727D+04 324145D+04 916754D+20 389400D+13 770095D+21 460259D+12 9 1003 435421D+03 503959D+04 444231D+04 125639D+21 501600D+13 105619D+22 592876D+12 8 1135 505483D+03 585050D+04 515711D+04 145855D+21 567600D+13 122644D+22 670886D+12 7 1195 549399D+03 635879D+04 560516D+04 158526D+21 597300D+13 133246D+22 705990D+12 6 1214 594204D+03 687736D+04 606226D+04 171454D+21 607200D+13 144275D+22 717692D+12 5 1234 606630D+03 702118D+04 618904D+04 175040D+21 617100D+13 147295D+22 729393D+12 4 1241 595072D+03 688741D+04 607113D+04 171705D+21 620400D+13 144460D+22 733294D+12 3 1214 557557D+03 645320D+04 568838D+04 160880D+21 607200D+13 135167D+22 717692D+12 2 1102 479778D+03 555299D+04 489486D+04 138438D+21 551100D+13 116373D+22 651383D+12 1 878 359583D+03 416184D+04 366858D+04 103756D+21 438900D+13 871773D+21 518766D+12 ---------------------------------------------------------------------------------------------------- STRESS(RADIAL) (MPA) IWROD= 1 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 -36 -36 -37 -37 -38 -38 -39 -39 -40 -40 -41 -42 -42 -43 -43 -44 -45 -45 -46 -46 -47 -48 -49 -49 -50 -51 -52 -52 -53 -54 -55 -56 -57 -58 -59 -60 9 -23 -24 -24 -25 -25 -26 -26 -27 -27 -28 -28 -29 -29 -30 -31 -31 -32 -32 -33 -34 -34 -35 -35 -36 -37 -37 -38 -39 -40 -41 -42 -43 -44 -45 -46 -48 8 -15 -15 -16 -16 -17 -17 -17 -18 -19 -19 -20 -20 -21 -21 -22 -22 -23 -23 -24 -24 -25 -26 -26 -27 -28 -29 -30 -31 -32 -33 -34 -35 -36 -37 -39 -40 7 -11 -11 -11 -12 -12 -13 -13 -13 -14 -14 -15 -15 -16 -16 -17 -17 -18 -18 -19 -20 -21 -21 -22 -23 -24 -25 -26 -27 -28 -29 -30 -31 -32 -33 -35 -36 6 -05 -05 -06 -06 -07 -07 -08 -08 -09 -09 -10 -10 -11 -11 -12 -13 -13 -14 -15 -15 -16 -17 -18 -19 -19 -20 -21 -22 -23 -24 -25 -27 -28 -29 -30 -32 5 -06 -06 -06 -07 -07 -08 -08 -09 -09 -10 -10 -11 -11 -12 -13 -13 -14 -15 -15 -16 -17 -18 -19 -19 -20 -21 -22 -23 -24 -25 -26 -28 -29 -30 -32 -33 4 -09 -09 -09 -10 -10 -11 -11 -12 -12 -13 -14 -14 -15 -15 -16 -17 -17 -18 -19 -20 -20 -21 -22 -23 -24 -25 -26 -27 -28 -29 -31 -32 -33 -35 -36 -38 3 -11 -12 -12 -13 -13 -14 -14 -15 -15 -16 -16 -17 -18 -18 -19 -20 -21 -21 -22 -23 -24 -25 -26 -27 -28 -29 -30 -31 -32 -33 -35 -36 -37 -39 -40 -42 2 -21 -21 -22 -22 -23 -23 -24 -24 -25 -25 -26 -26 -27 -28 -28 -29 -30 -31 -31 -32 -33 -34 -35 -36 -37 -38 -39 -41 -42 -43 -44 -45 -47 -48 -50 -51 1 -36 -37 -37 -37 -38 -39 -39 -40 -40 -41 -41 -42 -43 -43 -44 -44 -45 -46 -46 -47 -48 -49 -50 -51 -52 -53 -54 -55 -56 -57 -58 -59 -60 -62 -63 -64 SEGMENT NUM 10 -101 -108 -114 -120 -127 -133 -139 -148 -154 -154 9 -91 -99 -107 -114 -122 -129 -136 -147 -154 -154 8 -84 -93 -101 -110 -118 -126 -134 -146 -154 -154 7 -80 -90 -99 -108 -116 -125 -133 -146 -154 -154 6 -76 -87 -96 -105 -114 -123 -132 -145 -154 -154 5 -78 -88 -97 -106 -115 -124 -133 -146 -154 -154 4 -82 -91 -100 -108 -117 -125 -134 -146 -154 -154 3 -85 -94 -102 -111 -119 -127 -135 -146 -154 -154 2 -94 -102 -109 -116 -123 -130 -137 -147 -154 -154 1 -105 -112 -117 -123 -129 -134 -140 -148 -154 -154 ---------------------------------------------------------------------------------------------------- STRESS(HOOP) (MPA) IWROD= 2 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 -36 -38 -40 -41 -43 -45 -47 -48 -50 -52 -54 -56 -59 -61 -63 -66 -68 -71 -73 -76 -76 -79 -82 -85 -88 -91 -94 -98 -102 -105 -109 -114 -118 -123 -128 -134 9 -23 -25 -27 -28 -30 -32 -33 -35 -37 -39 -41 -43 -46 -48 -50 -53 -55 -58 -59 -53 -56 -60 -63 -67 -71 -75 -80 -84 -89 -95 -101 -111 -126 -136 -146 -158 8 -15 -17 -18 -19 -21 -23 -24 -26 -28 -30 -32 -34 -36 -38 -37 -38 -40 -44 -47 -50 -54 -57 -61 -65 -69 -73 -78 -83 -88 -94 -100 -107 -114 -123 -133 -147 7 -11 -12 -13 -15 -16 -18 -19 -21 -23 -22 -24 -26 -29 -31 -34 -36 -39 -42 -45 -48 -52 -55 -59 -63 -67 -72 -76 -81 -87 -92 -99 -105 -113 -122 -132 -146 6 -05 -07 -08 -09 -11 -12 -14 -16 -18 -20 -22 -24 -26 -28 -31 -33 -36 -39 -42 -45 -48 -52 -55 -59 -63 -67 -72 -77 -82 -88 -94 -100 -108 -116 -126 -139
JAEA-DataCode 2013-009
- 204 -
5 -06 -07 -09 -10 -12 -13 -15 -17 -19 -20 -22 -25 -27 -29 -32 -34 -37 -40 -43 -46 -50 -53 -57 -61 -65 -70 -75 -80 -85 -91 -97 -104 -112 -121 -132 -145 4 -09 -10 -12 -13 -15 -17 -18 -20 -22 -24 -27 -29 -31 -34 -36 -39 -42 -45 -48 -52 -55 -59 -63 -67 -72 -76 -81 -87 -92 -98 -105 -112 -120 -129 -139 -153 3 -11 -14 -15 -17 -18 -20 -21 -22 -25 -28 -30 -33 -35 -38 -41 -44 -47 -50 -54 -57 -61 -65 -69 -74 -78 -83 -88 -94 -100 -106 -113 -120 -128 -137 -148 -161 2 -21 -23 -24 -26 -28 -29 -31 -33 -35 -37 -39 -41 -44 -46 -48 -53 -57 -61 -65 -69 -73 -77 -81 -85 -90 -94 -100 -105 -110 -116 -122 -129 -136 -144 -154 -166 1 -36 -38 -40 -42 -43 -45 -47 -49 -51 -53 -55 -58 -60 -62 -65 -68 -70 -73 -75 -80 -85 -89 -93 -96 -100 -104 -109 -113 -117 -122 -127 -133 -139 -145 -152 -160 SEGMENT NUM 10 -450 -461 -473 -485 -496 -508 -519 -527 -162 -162 9 -524 -535 -546 -557 -568 -579 -589 -596 -163 -164 8 -569 -581 -593 -606 -618 -631 -644 -652 -163 -164 7 -593 -605 -618 -631 -644 -657 -671 -680 -164 -165 6 -627 -639 -651 -664 -677 -690 -703 -712 -164 -166 5 -619 -631 -643 -656 -668 -681 -694 -703 -164 -166 4 -589 -600 -612 -625 -637 -650 -663 -672 -164 -165 3 -554 -567 -580 -593 -607 -621 -634 -645 -163 -164 2 -498 -510 -522 -534 -546 -559 -571 -580 -163 -163 1 -420 -431 -444 -456 -468 -480 -493 -502 -162 -162 ---------------------------------------------------------------------------------------------------- STRESS(AXIAL) (MPA) IWROD= 3 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 08 08 09 09 09 10 10 11 11 12 12 12 13 13 13 10 9 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 32 34 34 34 34 35 35 35 35 36 36 35 -00 -00 -00 -00 -00 8 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 21 21 20 20 19 19 18 18 17 17 16 16 16 16 16 16 16 16 17 18 16 7 00 00 00 00 00 00 00 00 00 14 15 15 15 14 13 12 11 11 10 09 08 07 07 06 05 05 04 04 03 03 02 02 02 02 02 03 6 18 17 16 15 14 13 12 11 10 09 08 07 07 06 05 04 03 02 01 00 -01 -02 -03 -04 -05 -06 -08 -09 -10 -11 -12 -13 -14 -15 -15 -13 5 15 14 13 12 11 10 09 09 08 07 06 05 04 03 02 01 00 -01 -02 -03 -05 -06 -08 -09 -11 -12 -14 -16 -18 -20 -22 -24 -26 -28 -29 -29 4 12 11 10 09 08 07 06 05 04 03 02 02 01 -00 -01 -02 -03 -05 -06 -08 -10 -12 -14 -16 -18 -20 -22 -24 -27 -29 -31 -34 -36 -38 -40 -40 3 12 00 00 00 00 00 00 07 06 05 03 02 01 00 -01 -02 -03 -04 -06 -08 -09 -11 -13 -15 -17 -19 -21 -23 -25 -27 -29 -31 -33 -34 -35 -34 2 00 00 00 00 00 00 00 00 00 00 00 00 00 00 05 03 01 00 -01 -02 -03 -05 -06 -07 -08 -09 -10 -11 -12 -12 -13 -13 -14 -13 -12 -10 1 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 15 14 12 11 11 10 10 10 10 10 10 10 10 10 11 11 11 12 SEGMENT NUM 10 -428 -443 -458 -474 -489 -504 -519 -533 -160 -160 9 -439 -457 -474 -492 -509 -527 -545 -562 -160 -161 8 -436 -453 -471 -489 -507 -526 -545 -564 -161 -161 7 -427 -444 -461 -479 -497 -515 -533 -552 -161 -162 6 -420 -436 -453 -469 -486 -504 -521 -539 -161 -162 5 -408 -424 -439 -456 -472 -488 -505 -523 -161 -162 4 -390 -406 -422 -437 -454 -470 -487 -504 -161 -162 3 -383 -399 -416 -433 -451 -469 -487 -505 -161 -161 2 -396 -413 -430 -447 -465 -483 -501 -519 -160 -161 1 -427 -443 -458 -474 -490 -505 -521 -537 -161 -161 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(RADIAL) (001) IWROD= 12 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 383 387 390 393 396 399 402 404 407 409 411 413 415 417 419 420 422 423 425 425 441 444 437 430 423 417 411 406 401 397 393 389 386 382 379 376 9 01 31 58 83 108 133 157 181 205 228 250 272 294 315 336 357 376 395 417 505 595 602 584 568 553 542 532 525 520 518 517 521 533 545 560 574 8 -392 -323 -269 -221 -175 -132 -90 -48 -07 33 73 112 150 188 243 340 455 590 722 855 955 954 915 878 844 812 784 757 733 711 693 680 671 668 670 676 7 -1088 -728 -535 -411 -327 -264 -211 -163 -117 -47 60 164 275 393 521 656 784 911 1041 1174 1268 1257 1203 1152 1104 1062 1019 978 939 903 869 839 813 793 779 771 6 -1717 -1315 -1008 -778 -590 -425 -281 -144 -16 107 230 354 477 594 711 832 955 1081 1209 1341 1432 1421 1360 1300 1241 1184 1131 1079 1031 986 943 905 871 842 822 814 5 -1948 -1463 -1087 -767 -526 -340 -186 -48 78 200 321 441 556 670 787 908 1031 1155 1284 1416 1507 1493 1432 1368 1306 1246 1189 1135 1083 1036 992 951 913 880 853 835 4 -1554 -1197 -947 -745 -571 -411 -253 -115 09 126 246 371 500 626 747 870 995 1123 1253 1386 1480 1465 1405 1347 1289 1232 1177 1126 1078 1033 991 951 915 882 856 838
JAEA-DataCode 2013-009
- 205 -
3 -1131 -819 -572 -422 -325 -255 -200 -137 -42 69 174 284 397 516 639 773 902 1029 1160 1291 1385 1374 1316 1262 1212 1165 1118 1074 1032 992 955 921 891 864 841 821 2 -169 -125 -88 -52 -17 17 51 84 117 149 181 212 242 272 306 396 502 621 756 890 989 992 954 919 886 855 826 800 775 751 730 712 694 679 666 658 1 334 343 351 359 367 374 381 388 395 401 408 414 419 425 430 435 440 445 461 539 623 632 614 597 582 567 553 539 527 515 505 494 485 476 467 459 SEGMENT NUM 10 1226 1184 1146 1111 1077 1045 1015 974 16 15 9 1539 1488 1443 1400 1359 1320 1282 1233 261 261 8 1759 1701 1649 1600 1554 1510 1469 1413 431 430 7 1907 1845 1789 1736 1686 1639 1594 1534 546 544 6 2097 2028 1968 1910 1856 1804 1754 1688 693 691 5 2091 2023 1962 1904 1850 1798 1748 1682 686 684 4 1986 1920 1862 1807 1755 1706 1659 1596 603 602 3 1814 1754 1700 1649 1602 1556 1513 1455 471 471 2 1516 1466 1420 1378 1337 1298 1261 1212 242 241 1 1210 1168 1131 1096 1063 1031 1001 961 05 05 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(HOOP) (001) IWROD= 13 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 383 384 385 386 387 388 389 390 391 392 393 394 395 395 396 397 398 398 399 400 401 402 402 403 404 404 404 404 404 404 404 404 403 403 403 403 9 01 06 15 23 32 40 49 57 65 73 81 89 97 105 113 121 128 136 143 151 161 171 181 189 197 204 210 216 222 227 231 236 241 245 250 254 8 -392 -380 -361 -343 -326 -310 -294 -278 -263 -248 -234 -219 -205 -191 -176 -161 -144 -125 -103 -80 -56 -32 -10 09 27 43 57 70 82 93 103 112 121 129 137 145 7 -1088 -1026 -937 -865 -806 -757 -716 -679 -647 -616 -586 -555 -523 -491 -457 -423 -388 -352 -316 -279 -242 -206 -174 -145 -119 -95 -73 -54 -36 -19 -04 09 22 34 45 55 6 -1717 -1648 -1540 -1440 -1350 -1270 -1196 -1129 -1065 -1005 -948 -892 -839 -787 -737 -687 -639 -591 -543 -496 -449 -405 -365 -328 -295 -265 -238 -214 -191 -171 -152 -135 -119 -104 -90 -78 5 -1948 -1865 -1733 -1609 -1495 -1394 -1303 -1221 -1146 -1077 -1011 -949 -890 -834 -779 -725 -673 -622 -572 -522 -473 -426 -384 -345 -311 -279 -251 -225 -201 -180 -160 -142 -125 -110 -96 -82 4 -1554 -1493 -1399 -1313 -1236 -1165 -1098 -1035 -976 -919 -865 -813 -762 -712 -663 -615 -567 -520 -473 -427 -381 -337 -297 -261 -229 -199 -172 -148 -126 -106 -87 -70 -55 -40 -27 -15 3 -1131 -1078 -993 -916 -852 -798 -752 -712 -674 -637 -600 -563 -526 -489 -452 -414 -375 -336 -297 -258 -218 -181 -146 -115 -88 -62 -39 -19 00 18 34 48 61 74 85 96 2 -169 -161 -149 -137 -125 -113 -101 -90 -78 -67 -55 -44 -33 -22 -11 01 14 30 48 68 90 111 130 148 163 177 190 201 212 221 230 238 245 252 258 263 1 334 336 338 341 344 346 349 351 353 356 358 361 363 365 367 369 372 374 376 379 384 390 395 399 403 407 410 412 414 416 418 419 420 421 422 422 SEGMENT NUM 10 -786 -748 -714 -682 -651 -623 -595 -558 -534 -534 9 -926 -879 -837 -798 -761 -726 -692 -647 -617 -616 8 -1029 -976 -929 -885 -843 -803 -765 -714 -680 -679 7 -1114 -1056 -1006 -958 -913 -870 -829 -773 -736 -734 6 -1240 -1177 -1121 -1069 -1019 -971 -926 -864 -824 -820 5 -1245 -1181 -1126 -1073 -1023 -976 -931 -869 -828 -825 4 -1180 -1120 -1067 -1017 -969 -924 -882 -823 -785 -782 3 -1075 -1020 -972 -926 -882 -841 -802 -748 -714 -712 2 -916 -870 -829 -790 -754 -719 -686 -641 -612 -611 1 -766 -729 -695 -664 -634 -606 -579 -542 -519 -519 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(AXIAL) (001) IWROD= 14 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 1451 1432 1413 1394 1376 1358 1340 1322 1305 1288 1270 1253 1236 1220 1203 1187 1171 1155 1139 1123 1129 1115 1110 1104 1098 1092 1085 1078 1071 1064 1055 1047 1037 1025 1011 983 9 3146 3089 3033 2977 2922 2868 2815 2762 2709 2657 2606 2556 2506 2457 2408 2361 2313 2267 2212 2252 2130 2094 2086 2078 2068 2057 2045 2031 2014 1994 1968 1763 1719 1677 1630 1581 8 4500 4392 4294 4202 4113 4027 3943 3861 3779 3699 3619 3541 3463 3387 3289 3245 3081 2893 2710 2519 2359 2309 2304 2298 2291 2284 2276 2267 2257 2245 2231 2214 2194 2171 2140 2082 7 6183 5744 5439 5218 5048 4909 4786 4674 4567 4506 4338 4168 3988 3802 3603 3398 3201 3004 2804 2599 2429 2374 2371 2367 2363 2358 2353 2346 2339 2331 2321 2309 2294 2276 2252 2220 6 6939 6708 6477 6250 6022 5793 5564 5337 5116 4900 4685 4470 4257 4052 3849 3644 3437 3229 3018 2803 2627 2571 2569 2567 2564 2561 2557 2553 2548 2542 2535 2526 2514 2497 2474 2441 5 6958 6726 6495 6264 6035 5808 5582 5356 5133 4912 4693 4476 4265 4059 3851 3642 3432 3221 3007 2790 2612 2553 2553 2551 2549 2547 2545 2542 2538 2534 2529 2522 2512 2497 2475 2444 4 6826 6594 6364 6134 5903 5667 5425 5195 4979 4769 4558 4344 4128 3915 3708 3502 3294 3085 2874 2658 2481 2422 2421 2420 2417 2414 2411 2408 2404 2399 2394 2386 2376 2362 2341 2313 3 6349 5923 5569 5318 5129 4978 4849 4750 4575 4385 4203 4018 3829 3636 3438 3229 3026 2825 2622 2415 2242 2186 2184 2181 2178 2175 2171 2166 2161 2155 2147 2138 2126 2111 2091 2065 2 3834 3759 3685 3612 3541 3470 3401 3332 3264 3197 3130 3065 3000 2936 2894 2744 2584 2413 2226 2039 1879 1828 1824 1820 1815 1810 1805 1798 1790 1780 1770 1757 1742 1725 1706 1681
JAEA-DataCode 2013-009
- 206 -
1 1865 1837 1809 1782 1755 1728 1702 1676 1650 1625 1600 1575 1550 1526 1502 1478 1455 1431 1469 1355 1234 1196 1192 1188 1183 1179 1174 1168 1162 1156 1150 1142 1135 1127 1118 1108 SEGMENT NUM 10 439 439 439 439 439 439 439 439 439 439 9 347 347 347 347 347 347 347 347 347 347 8 278 278 278 278 278 278 278 278 278 278 7 243 243 243 243 243 243 243 243 243 243 6 208 208 208 208 208 208 208 208 208 208 5 226 226 226 226 226 226 226 226 226 226 4 257 257 257 257 257 257 257 257 257 257 3 297 297 297 297 297 297 297 297 297 297 2 385 385 385 385 385 385 385 385 385 385 1 461 461 461 461 461 461 461 461 461 461 --------------------------------------------------------------------------------------------------------------------- DISPLACEMENT OF NODES (MICRON) GAP IWROD=18 --------------------------------------------------------------------------------------------------------------------- (R-DIRECTION OF Pellet) 10 00 26 37 46 53 59 65 70 75 80 85 89 93 97 101 105 109 112 116 119 122 126 129 132 135 138 141 144 146 149 151 154 156 158 161 163 165 0000 9 00 00 01 02 04 05 07 10 12 14 17 19 22 25 28 31 34 37 40 44 48 52 57 61 65 69 72 76 79 82 86 89 92 95 99 102 105 -0000 8 00 -27 -36 -42 -46 -49 -51 -52 -52 -52 -52 -51 -50 -49 -47 -45 -42 -38 -33 -27 -21 -14 -07 -00 06 12 17 23 28 32 37 41 45 49 53 57 61 0000 7 00 -74 -95 -107 -114 -119 -123 -126 -128 -129 -130 -129 -128 -125 -121 -117 -111 -104 -97 -89 -80 -70 -61 -52 -44 -36 -29 -22 -16 -10 -04 01 06 11 16 20 25 -0000 6 -00 -117 -155 -176 -191 -200 -206 -210 -212 -212 -211 -209 -205 -200 -195 -188 -181 -173 -164 -155 -144 -134 -123 -113 -104 -96 -88 -80 -73 -66 -60 -54 -49 -44 -39 -34 -29 0000 5 00 -133 -175 -198 -212 -221 -226 -228 -229 -228 -226 -222 -218 -212 -206 -199 -191 -183 -173 -163 -152 -141 -130 -119 -110 -101 -92 -84 -77 -70 -63 -57 -51 -46 -41 -36 -31 0000 4 -00 -106 -140 -161 -174 -183 -189 -193 -194 -194 -193 -190 -186 -182 -176 -169 -162 -153 -144 -134 -123 -112 -101 -91 -82 -73 -65 -57 -49 -42 -36 -30 -24 -19 -13 -08 -04 0000 3 00 -77 -100 -113 -121 -126 -130 -132 -134 -134 -134 -132 -129 -125 -120 -115 -108 -100 -92 -83 -73 -62 -52 -43 -34 -25 -18 -10 -03 03 10 16 21 27 32 37 41 0000 2 -00 -12 -15 -17 -18 -18 -18 -17 -16 -15 -13 -11 -09 -07 -04 -02 02 06 11 17 24 32 39 46 52 58 64 70 75 80 84 89 93 97 101 105 109 0000 1 -00 23 33 40 47 53 58 63 68 73 77 81 86 90 94 97 101 105 109 112 116 121 126 130 134 138 142 146 149 153 156 159 162 165 168 171 173 0000 (R-DIRECTION OF Cladding) 10 -335 -324 -439 -554 -669 -784 -900 -1016 -376 -285 -195 9 -395 -381 -501 -621 -741 -861 -982 -1103 -473 -338 -204 8 -439 -424 -548 -673 -798 -924 -1050 -1176 -557 -381 -204 7 -475 -459 -588 -718 -848 -978 -1109 -1241 -631 -418 -206 6 -529 -511 -648 -786 -924 -1062 -1201 -1340 -747 -477 -207 5 -531 -513 -650 -788 -927 -1066 -1205 -1344 -752 -480 -208 4 -504 -486 -617 -749 -881 -1013 -1146 -1279 -673 -446 -219 3 -459 -443 -566 -690 -813 -938 -1062 -1187 -565 -395 -225 2 -391 -378 -494 -610 -727 -844 -962 -1079 -443 -329 -216 1 -327 -316 -428 -540 -652 -765 -877 -990 -344 -272 -201 (Z-DIRECTION) --------- ----------------- ----------------- SEG NUM PELLET CLADDING --------- ----------------- ----------------- 3320349 (Plenum) 10 17978018 3139625 9 17011895 2700241 8 15111354 2353547 7 13062890 2075605 6 10982299 1832555 5 8725090 1624646 4 6498207 1399120 3 4400904 1142594 2 2524119 845249 1 972466 460642 --------------------------------------------------------------------------------------------------------------------- DISPLACEMENT INCREMENT OF NODES (MICRON) GAP IWROD=18 --------------------------------------------------------------------------------------------------------------------- (R-DIRECTION OF Pellet) 10 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 9 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -0000
JAEA-DataCode 2013-009
- 207 -
8 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 7 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -0000 6 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 5 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 4 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 3 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 2 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 1 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 (R-DIRECTION OF Cladding) 10 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 9 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 8 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 7 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 6 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 5 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 4 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 3 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 2 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 1 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 (Z-DIRECTION) --------- ----------------- ----------------- SEG NUM PELLET CLADDING --------- ----------------- ----------------- 1253 (Plenum) 10 1222 1222 9 1090 1090 8 0947 0947 7 0808 0808 6 0680 0680 5 0592 0592 4 0511 0511 3 0425 0425 2 0307 0307 1 0154 0154 STAGE NO 618 PELLET DISPLACEMENT (MICRONS) CLADDING DISPLACEMENT (MICRONS) CLEARANCE CONTACT THERMAL ELASTIC DENSIFI IRRAD RELOC DISPLA THERMAL ELASTIC DISPLA NODE (MICRONS) FORCE(MPA) EXPANS DEFORM CREEP CATION SWELL ATION CEMENT EXPANS DEFORM CREEP CEMENT 10 0000 5971 1265 -090 -869 -2648 2827 1164 1650 822 -138 -3787 -3350 9 -0000 4827 1528 -063 -2705 -2707 3813 1186 1051 851 -177 -4321 -3949 8 -0000 4043 1719 -045 -3905 -2720 4356 1204 609 872 -204 -4717 -4391 7 -0000 3668 1830 -035 -4700 -2725 4659 1217 246 885 -220 -5049 -4754 6 -0000 3223 1911 -024 -5595 -2728 4910 1234 -292 899 -240 -5542 -5292 5 0000 3360 1945 -026 -5704 -2728 4973 1230 -311 900 -239 -5564 -5311 4 -0000 3799 1923 -032 -5328 -2728 4914 1216 -036 889 -224 -5313 -5036 3 -0000 4222 1835 -039 -4579 -2725 4710 1211 413 872 -206 -4899 -4587 2 -0000 5156 1632 -059 -3115 -2717 4163 1187 1091 847 -171 -4286 -3909 1 -0000 6422 1342 -091 -1190 -2678 3185 1164 1733 817 -122 -3719 -3267 OUTPUT ---STAGE--- 619 IFEM = 6 ---------------------------------------------------------------------------------------------------- |THERMAL ANALYSIS INFORMATION | | STAGE NO 619 | | TIME (HMSMS) 363855730374 | | COOLANT TEMPERATURE 28500 DEGC | | COOLANT PRESSURE 154D+01 MPA | ---------------------------------------------------------------------------------------------------- LHR BURN UP GAP CONDUCTANCE (WCM2-K) TEMPERATURE (C) CLEARANCE CONTACT NODE (WCM) (MWDTU) TOTAL GAS SOLID RAD PC PS CI CO (MICRONS) FORCE(MPA) NODE 10 779 367728 9573 1237 0033 00034 5022 3225 3194 3062 0000 5970 10 9 1003 503960 9542 1242 0022 00036 5968 3344 3304 3136 0000 4827 9 8 1135 585051 9534 1246 0017 00038 6610 3429 3383 3196 0000 4043 8 7 1195 635880 9531 1250 0014 00039 6963 3480 3432 3237 0000 3668 7 6 1214 687737 9529 1252 0012 00040 7203 3529 3480 3285 0000 3224 6 5 1234 702119 9528 1255 0012 00040 7311 3537 3487 3288 0000 3360 5 4 1241 688742 9524 1254 0014 00039 7257 3499 3449 3247 0000 3800 4 3 1214 645321 9521 1249 0016 00038 6996 3436 3387 3186 0000 4222 3
JAEA-DataCode 2013-009
- 208 -
2 1102 555300 9526 1245 0022 00036 6345 3338 3293 3108 0000 5156 2 1 878 416184 9550 1240 0033 00034 5329 3212 3177 3028 0000 6422 1 BURN UP PELLET DISPLACEMENT (MICRONS) CLADDING DISPLACEMENT (MICRONS) (FISSCC THERMAL DENSIFI IRRAD RELOC DISPLA THERMAL ELASTIC DISPLA NODE CSFR PFAC 1020) EXPANS CREEP CATION SWELL ATION CEMENT EXPANS DEFORM CREEP CEMENT 10 00000 00000 910 1265 -869 -2648 2827 1164 1649 822 -138 -3787 -3351 9 00000 00000 1247 1528 -2705 -2707 3813 1186 1051 851 -177 -4321 -3949 8 00000 00000 1448 1719 -3905 -2720 4356 1204 609 872 -204 -4717 -4391 7 00000 00000 1574 1830 -4700 -2725 4659 1217 246 885 -220 -5049 -4754 6 00000 00000 1702 1911 -5595 -2728 4910 1234 -292 899 -240 -5542 -5292 5 00000 00000 1737 1945 -5704 -2728 4973 1230 -311 900 -239 -5564 -5311 4 00000 00000 1704 1923 -5328 -2728 4914 1216 -036 889 -224 -5313 -5036 3 00000 00000 1597 1835 -4579 -2725 4710 1211 413 872 -206 -4899 -4587 2 00000 00000 1374 1632 -3115 -2717 4163 1187 1091 847 -171 -4286 -3909 1 00000 00000 1030 1342 -1190 -2678 3185 1164 1733 817 -122 -3719 -3267 CLAD SURFACE COOLANT COOLANT COOLANT CLAD SURFACE CLAD SURFACE HEAT TRANS CLAD OUTER CORROSION NODE TEMP(C) TEMP(C) ENTHALPY(JKG) QUALTY(-) HF(WCM2) COEF(WCM2K) MODE (MICROND) THICKNESS(MIC) 10 3014 2896 128346D+06 -0352(MSUBCOOL) 250161D+01 213443D+00 1 831541D-03 1816577 9 3043 2892 128137D+06 -0354(MSUBCOOL) 322089D+01 213318D+00 1 113010D-02 2701419 8 3059 2888 127887D+06 -0356(MSUBCOOL) 364307D+01 213169D+00 1 143834D-02 3534082 7 3062 2882 127615D+06 -0359(MSUBCOOL) 383220D+01 213007D+00 1 169085D-02 4261795 6 3060 2877 127333D+06 -0362(MSUBCOOL) 389335D+01 212839D+00 1 203958D-02 5404640 5 3058 2872 127047D+06 -0365(MSUBCOOL) 395673D+01 212670D+00 1 206495D-02 5447857 4 3054 2866 126758D+06 -0368(MSUBCOOL) 397979D+01 212499D+00 1 176017D-02 4552738 3 3044 2861 126471D+06 -0371(MSUBCOOL) 389749D+01 212330D+00 1 138362D-02 3411542 2 3022 2856 126200D+06 -0374(MSUBCOOL) 353954D+01 212171D+00 1 100823D-02 2274663 1 2984 2851 125968D+06 -0376(MSUBCOOL) 282018D+01 212035D+00 1 719058D-03 1438410 0 INITIAL GAS (MOL) = 414D-03 0 FISSION GAS RESULT 0 LOCAL FISSION GAS RELEASE FRACTION (AXIAL NODE) 1 001306 2 004371 3 009150 4 012529 5 014209 6 012980 7 008746 8 004846 9 002029 10 000517 0 ROD AVERAGE FISSION GAS = 007950 FRACTIONS OF GAS MIXTURE (PERCENT) AXIAL NODE RELEASE FRACTION 1 2 3 4 5 6 7 8 9 10 ROD GAS PRESSURE ( MPA ) = 3869 HE 555 555 555 555 555 555 555 555 555 555 ROD GAS VOLUME ( CM3 ) = 8502 N2 00 00 00 00 00 00 00 00 00 00 (GAPPLENUM)= 1295 7207 KR 58 58 58 58 58 58 58 58 58 58 TOTAL GAS ( MOL ) = 655D-03 XE 387 387 387 387 387 387 387 387 387 387 ROD PRS(MPA) 3869 3869 3869 3869 3869 3869 3869 3869 3869 3869 0 RELEASED IODINE ( GRAMCM2 ) = 635D-05 (AVERAGE) 123D-04 (PEAK) 0 (MOL) HE N2 KR XE TOTAL PRODUCED GAS 374D-04 000D+00 490D-03 328D-02 381E-02 RELEASED GAS 462D-05 000D+00 390D-04 261D-03 304E-03 ROD GAS 418D-03 000D+00 390D-04 261D-03 655E-03 0 RADIAL TEMPERATURE DISTRIBUTION AT AXIAL NODE OF 6 PELLET GAP CLAD 1234567891011 123 720 717 707 690 666 635 598 553 501 440 353 348 338 328 === OPTIONAL OUTPUT (IN ELEMENT AVERAGE) === ---------------------------------------------------------------------------------------------------- | TEMPERATURE DISTRIBUTION IN THE FUEL (DEGC) IWTHE= 1 | ---------------------------------------------------------------------------------------------------- SEG 10 50133 49786 49093 48054 46670 44942 42867 40437 37624 34184 9 59559 59061 58065 56571 54581 52093 49105 45601 41524 36386 8 65949 65351 64155 62361 59971 56982 53389 49170 44248 37942 7 69467 68817 67517 65567 62966 59713 55800 51199 45819 38858 6 71861 71183 69824 67786 65065 61658 57555 52722 47053 39643 5 72931 72235 70842 68751 65960 62466 58255 53295 47475 39847 4 72392 71697 70306 68218 65433 61946 57748 52804 47009 39434 3 69792 69129 67802 65810 63155 59833 55837 51138 45642 38517 2 63307 62739 61604 59901 57632 54797 51391 47393 42735 36803 1 53187 52781 51968 50750 49128 47102 44669 41821 38518 34434 ---------------------------------------------------------------------------------------------------- | RADIUS OF INTRAGRANULAR GAS BUBBLE (ANGSTROM) IWTHE= 4 | ---------------------------------------------------------------------------------------------------- SEG 10 345 345 345 346 347 349 351 355 362 399 9 389 389 389 390 391 393 396 400 409 457 8 411 411 412 413 414 416 419 424 434 488 7 402 404 414 423 427 429 432 437 448 506 6 367 371 386 407 429 442 445 451 462 523 5 362 365 378 401 427 444 449 454 466 528 4 374 378 392 412 432 442 445 451 462 523 3 400 403 413 424 429 432 435 440 451 509 2 403 403 404 405 406 408 411 415 425 477 1 361 362 362 363 364 366 368 372 380 421 ---------------------------------------------------------------------------------------------------- | FISSION GAS RELEASE RATE IN A RING () IWTHE= 14 | ---------------------------------------------------------------------------------------------------- SEG 10 050 050 050 050 050 050 050 050 050 055 9 050 050 050 050 050 050 050 050 050 483 8 050 050 050 050 050 050 050 050 050 1382 7 1312 1165 685 165 050 050 050 050 050 2533 6 3549 3378 2746 1748 643 053 050 050 050 2856 5 3896 3771 3233 2209 953 092 050 050 050 2949 4 3282 3099 2459 1509 493 050 050 050 050 2863 3 1513 1360 856 247 050 050 050 050 050 2591 2 050 050 050 050 050 050 050 050 050 1261 1 050 050 050 050 050 050 050 050 050 301
JAEA-DataCode 2013-009
- 209 -
---------------------------------------------------------------------------------------------------- BURNUP DISTRIBUTION IN THE FUEL (MWDT) IWTHE= 18 ---------------------------------------------------------------------------------------------------- SEG 10 324006 324729 325496 326304 327155 328040 328983 329987 331030 332108 9 434960 436250 437488 438744 440036 441357 442750 444226 445754 447330 8 499246 500926 502485 504044 505633 507246 508938 510729 512580 514488 7 538964 540904 542677 544439 546227 548036 549928 551929 553996 556127 6 579130 581345 583345 585322 587321 589339 591445 593670 595968 598337 5 590218 592510 594574 596612 598671 600748 602915 605204 607567 610004 4 579907 582128 584132 586113 588117 590138 592249 594478 596780 599154 3 546300 548290 550104 551904 553730 555577 557507 559548 561656 563830 2 475797 477330 478768 480213 481690 483194 484773 486445 488175 489957 1 363909 364820 365744 366703 367703 368736 369832 370997 372205 373452 ================================================================================================================================== MECHANICAL ANALYSIS INFORMATION OUTPUT STAGE NUMBER = 619 TIME = 36385 H 57 M 30 S3744 MS ROD GAS PRESS(MPA) = 3869 COOLANT PRESS(MPA) = 15400 AXIAL FORCE(N) = -8369844 ================================================================================================================================== ---- ------ -------------------------------------------------- ----------------- -------------------- ------------ SEG LHR B U R N U P FAST NEUTRON FLUX FAST NEUTRON FLUENCE FISSION RATE (WCM) (GJKGU) (MWDTU) (MWDTUO2) (FISSCC) (NCM2SEC) (NCM2) (FISSCCSEC) ---- ------ -------------------------------------------------- ----------------- -------------------- ------------ 10 779 317717D+03 367728D+04 324145D+04 916756D+20 389400D+13 770096D+21 460259D+12 9 1003 435422D+03 503960D+04 444232D+04 125639D+21 501600D+13 105619D+22 592876D+12 8 1135 505484D+03 585051D+04 515712D+04 145855D+21 567600D+13 122645D+22 670886D+12 7 1195 549400D+03 635880D+04 560517D+04 158527D+21 597300D+13 133247D+22 705990D+12 6 1214 594204D+03 687737D+04 606227D+04 171455D+21 607200D+13 144275D+22 717692D+12 5 1234 606631D+03 702119D+04 618905D+04 175040D+21 617100D+13 147296D+22 729393D+12 4 1241 595073D+03 688742D+04 607114D+04 171705D+21 620400D+13 144460D+22 733294D+12 3 1214 557558D+03 645321D+04 568839D+04 160881D+21 607200D+13 135167D+22 717692D+12 2 1102 479779D+03 555300D+04 489486D+04 138438D+21 551100D+13 116373D+22 651383D+12 1 878 359583D+03 416184D+04 366859D+04 103756D+21 438900D+13 871774D+21 518766D+12 ---------------------------------------------------------------------------------------------------- STRESS(RADIAL) (MPA) IWROD= 1 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 -36 -36 -37 -37 -38 -38 -39 -39 -40 -40 -41 -42 -42 -43 -43 -44 -45 -45 -46 -46 -47 -48 -48 -49 -50 -51 -52 -52 -53 -54 -55 -56 -57 -58 -59 -60 9 -23 -24 -24 -25 -25 -26 -26 -27 -27 -28 -28 -29 -29 -30 -31 -31 -32 -32 -33 -34 -34 -35 -35 -36 -37 -37 -38 -39 -40 -41 -42 -43 -44 -45 -46 -48 8 -15 -15 -16 -16 -17 -17 -17 -18 -18 -19 -20 -20 -21 -21 -22 -22 -23 -23 -24 -24 -25 -26 -26 -27 -28 -29 -30 -31 -32 -33 -34 -35 -36 -37 -39 -40 7 -11 -11 -11 -12 -12 -13 -13 -13 -14 -14 -15 -15 -16 -16 -17 -17 -18 -18 -19 -20 -21 -21 -22 -23 -24 -25 -26 -27 -28 -29 -30 -31 -32 -33 -35 -36 6 -05 -05 -06 -06 -07 -07 -08 -08 -09 -09 -10 -10 -11 -11 -12 -13 -13 -14 -15 -15 -16 -17 -18 -19 -19 -20 -21 -22 -23 -24 -25 -27 -28 -29 -30 -32 5 -06 -06 -06 -07 -07 -08 -08 -09 -09 -10 -10 -11 -11 -12 -13 -13 -14 -15 -15 -16 -17 -18 -19 -19 -20 -21 -22 -23 -24 -25 -26 -28 -29 -30 -32 -33 4 -09 -09 -09 -10 -10 -11 -11 -12 -12 -13 -14 -14 -15 -15 -16 -17 -17 -18 -19 -20 -20 -21 -22 -23 -24 -25 -26 -27 -28 -29 -31 -32 -33 -35 -36 -38 3 -11 -12 -12 -13 -13 -14 -14 -15 -15 -16 -16 -17 -18 -18 -19 -20 -21 -21 -22 -23 -24 -25 -26 -27 -28 -29 -30 -31 -32 -33 -35 -36 -37 -39 -40 -42 2 -21 -21 -22 -22 -23 -23 -24 -24 -25 -25 -26 -26 -27 -28 -28 -29 -30 -31 -31 -32 -33 -34 -35 -36 -37 -38 -39 -41 -42 -43 -44 -45 -47 -48 -50 -51 1 -36 -37 -37 -37 -38 -39 -39 -40 -40 -41 -41 -42 -43 -43 -44 -44 -45 -46 -46 -47 -48 -49 -50 -51 -52 -53 -54 -55 -56 -57 -58 -59 -60 -62 -63 -64 SEGMENT NUM 10 -101 -108 -114 -120 -127 -133 -139 -148 -154 -154 9 -91 -99 -107 -114 -122 -129 -136 -147 -154 -154 8 -84 -93 -101 -110 -118 -126 -134 -146 -154 -154 7 -80 -90 -99 -108 -116 -125 -133 -146 -154 -154 6 -76 -87 -96 -105 -114 -123 -132 -145 -154 -154 5 -78 -88 -97 -106 -115 -124 -133 -146 -154 -154 4 -82 -91 -100 -108 -117 -125 -134 -146 -154 -154 3 -85 -94 -102 -111 -119 -127 -135 -146 -154 -154 2 -94 -102 -109 -116 -123 -130 -137 -147 -154 -154 1 -105 -112 -117 -123 -129 -134 -140 -148 -154 -154 ---------------------------------------------------------------------------------------------------- STRESS(HOOP) (MPA) IWROD= 2 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 -36 -38 -40 -41 -43 -45 -47 -48 -50 -52 -54 -56 -59 -61 -63 -66 -68 -71 -73 -76 -76 -79 -82 -85 -88 -91 -94 -98 -102 -105 -109 -114 -118 -123 -128 -134 9 -23 -25 -27 -28 -30 -32 -33 -35 -37 -39 -41 -43 -46 -48 -50 -53 -55 -58 -59 -53 -56 -60 -63 -67 -71 -75 -80 -84 -89 -95 -101 -111 -126 -136 -146 -158 8 -15 -17 -18 -19 -21 -23 -24 -26 -28 -30 -32 -34 -36 -38 -37 -38 -40 -44 -47 -50 -54 -57 -61 -65 -69 -73 -78 -83 -88 -94 -100 -107 -114 -123 -133 -147 7 -11 -12 -13 -15 -16 -18 -19 -21 -23 -22 -24 -26 -29 -31 -34 -36 -39 -42 -45 -48 -52 -55 -59 -63
JAEA-DataCode 2013-009
- 210 -
-67 -72 -76 -81 -87 -92 -99 -105 -113 -122 -132 -146 6 -05 -07 -08 -09 -11 -12 -14 -16 -18 -20 -22 -24 -26 -28 -31 -33 -36 -39 -42 -45 -48 -52 -55 -59 -63 -67 -72 -77 -82 -88 -94 -100 -108 -116 -126 -139 5 -06 -07 -09 -10 -12 -13 -15 -17 -19 -20 -22 -25 -27 -29 -32 -34 -37 -40 -43 -46 -50 -53 -57 -61 -65 -70 -75 -80 -85 -91 -97 -104 -112 -121 -132 -145 4 -09 -10 -12 -13 -15 -17 -18 -20 -22 -24 -27 -29 -31 -34 -36 -39 -42 -45 -48 -52 -55 -59 -63 -67 -72 -76 -81 -87 -92 -98 -105 -112 -120 -129 -139 -153 3 -11 -14 -15 -17 -18 -20 -21 -22 -25 -28 -30 -33 -35 -38 -41 -44 -47 -50 -54 -57 -61 -65 -69 -74 -78 -83 -88 -94 -100 -106 -113 -120 -128 -137 -148 -161 2 -21 -23 -24 -26 -28 -29 -31 -33 -35 -37 -39 -41 -44 -46 -48 -53 -57 -61 -65 -69 -73 -77 -81 -85 -90 -94 -100 -105 -110 -116 -122 -129 -136 -144 -154 -166 1 -36 -38 -40 -42 -43 -45 -47 -49 -51 -53 -55 -58 -60 -62 -65 -68 -70 -73 -75 -80 -85 -89 -93 -96 -100 -104 -109 -113 -117 -122 -127 -133 -139 -145 -152 -160 SEGMENT NUM 10 -450 -462 -473 -485 -496 -508 -519 -527 -162 -162 9 -524 -535 -546 -557 -568 -579 -590 -596 -163 -164 8 -569 -581 -593 -606 -618 -631 -644 -652 -163 -164 7 -593 -605 -618 -631 -644 -657 -671 -680 -164 -165 6 -627 -639 -651 -664 -677 -690 -703 -712 -164 -166 5 -619 -631 -643 -656 -668 -681 -694 -703 -164 -166 4 -589 -600 -612 -625 -637 -650 -663 -672 -164 -165 3 -554 -567 -580 -593 -607 -621 -634 -645 -163 -164 2 -498 -510 -522 -534 -546 -559 -571 -580 -163 -163 1 -420 -431 -444 -456 -468 -480 -493 -502 -162 -162 ---------------------------------------------------------------------------------------------------- STRESS(AXIAL) (MPA) IWROD= 3 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 08 08 09 09 09 10 10 11 11 12 12 12 13 13 13 10 9 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 32 34 34 34 34 34 35 35 35 35 36 35 00 00 00 00 -00 8 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 21 21 20 20 19 19 18 18 17 17 16 16 16 16 16 16 16 16 17 18 16 7 00 00 00 00 00 00 00 00 00 14 15 15 15 14 13 12 11 11 10 09 08 07 07 06 05 05 04 04 03 03 02 02 02 02 02 03 6 18 17 16 15 14 13 12 11 10 09 08 07 07 06 05 04 03 02 01 00 -01 -02 -03 -04 -05 -06 -08 -09 -10 -11 -12 -13 -14 -15 -15 -13 5 15 14 13 12 11 10 09 09 08 07 06 05 04 03 02 01 00 -01 -02 -03 -05 -06 -08 -09 -11 -12 -14 -16 -18 -20 -22 -24 -26 -28 -29 -29 4 12 11 10 09 08 07 06 05 04 03 02 02 01 -00 -01 -02 -03 -05 -06 -08 -10 -12 -14 -16 -18 -20 -22 -24 -27 -29 -31 -34 -36 -38 -40 -40 3 11 00 00 00 00 00 00 07 06 05 03 02 01 00 -01 -02 -03 -04 -06 -08 -09 -11 -13 -15 -17 -19 -21 -23 -25 -27 -29 -31 -33 -34 -35 -34 2 00 00 00 00 00 00 00 00 00 00 00 00 00 00 05 03 01 00 -01 -02 -03 -05 -06 -07 -08 -09 -10 -11 -12 -12 -13 -13 -13 -13 -12 -10 1 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 15 14 12 11 11 10 10 10 10 10 10 10 10 10 11 11 11 12 SEGMENT NUM 10 -428 -443 -458 -474 -489 -504 -519 -533 -160 -160 9 -439 -457 -474 -492 -509 -527 -545 -562 -160 -161 8 -436 -453 -471 -489 -507 -526 -545 -564 -161 -161 7 -427 -444 -461 -479 -497 -515 -533 -552 -161 -162 6 -420 -436 -453 -469 -486 -504 -521 -539 -161 -162 5 -408 -424 -439 -456 -472 -488 -505 -523 -161 -162 4 -390 -406 -422 -437 -454 -470 -487 -504 -161 -162 3 -383 -400 -416 -433 -451 -469 -487 -505 -161 -161 2 -396 -413 -430 -447 -465 -483 -501 -519 -160 -161 1 -427 -443 -458 -474 -490 -505 -521 -537 -161 -161 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(RADIAL) (001) IWROD= 12 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 383 387 390 393 396 399 402 404 407 409 411 413 415 417 419 420 422 423 425 425 441 444 437 430 423 417 411 406 401 397 393 389 386 382 379 376 9 01 31 58 83 108 133 157 181 205 228 250 272 294 315 336 357 376 395 417 505 595 602 584 568 553 542 532 525 520 518 517 521 533 545 560 574 8 -392 -323 -269 -221 -176 -132 -90 -48 -07 33 73 112 150 188 243 340 455 590 722 855 955 954 915 878 844 812 784 757 733 711 693 680 671 668 670 676 7 -1088 -728 -535 -411 -327 -264 -211 -163 -117 -47 60 164 275 393 521 656 784 911 1041 1174 1268 1257 1203 1152 1104 1062 1019 978 939 903 869 839 813 793 779 771 6 -1717 -1315 -1008 -778 -590 -425 -281 -144 -16 107 230 354 477 594 711 832 955 1081 1209 1341 1432 1421 1360 1300 1241 1184 1131 1079 1031 986 943 905 871 842 822 814 5 -1948 -1463 -1087 -767 -526 -340 -186 -48 78 200 321 441 556 670 787 908 1031 1155 1284 1416 1507 1493 1432 1368
JAEA-DataCode 2013-009
- 211 -
1306 1246 1189 1135 1083 1036 992 951 913 880 853 835 4 -1554 -1197 -947 -745 -571 -411 -253 -115 09 126 246 371 500 626 747 870 995 1123 1253 1386 1480 1465 1405 1347 1289 1232 1177 1126 1078 1033 991 951 915 882 856 838 3 -1131 -819 -572 -422 -325 -255 -200 -137 -42 69 174 284 397 516 639 773 902 1029 1160 1291 1385 1374 1316 1262 1212 1165 1118 1074 1032 992 955 921 891 864 841 821 2 -169 -125 -88 -52 -17 17 51 84 117 149 181 212 242 272 306 396 502 621 756 890 989 992 954 919 886 855 826 800 775 751 730 712 694 679 666 658 1 334 343 351 359 367 374 381 388 395 401 408 414 419 425 430 435 440 445 461 539 623 632 614 598 582 567 553 539 527 515 505 494 485 476 467 459 SEGMENT NUM 10 1226 1184 1146 1111 1077 1045 1015 974 16 15 9 1539 1488 1443 1400 1359 1320 1282 1233 261 261 8 1759 1701 1649 1600 1554 1510 1469 1413 431 430 7 1907 1845 1789 1736 1686 1639 1594 1534 546 544 6 2097 2028 1968 1910 1856 1804 1754 1688 693 691 5 2091 2023 1962 1904 1850 1798 1748 1682 686 684 4 1986 1920 1862 1807 1755 1706 1659 1596 603 602 3 1814 1754 1700 1650 1602 1556 1513 1455 471 471 2 1516 1466 1420 1378 1337 1298 1261 1212 242 241 1 1210 1168 1131 1096 1063 1031 1001 961 05 05 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(HOOP) (001) IWROD= 13 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 383 384 385 386 387 388 389 390 391 392 393 394 395 395 396 397 398 398 399 400 401 402 402 403 404 404 404 404 404 404 404 404 403 403 403 403 9 01 06 15 23 32 40 49 57 65 73 81 89 97 105 113 121 128 136 143 151 161 171 181 189 197 204 210 216 222 227 231 236 241 245 250 254 8 -392 -380 -361 -343 -326 -310 -294 -278 -263 -248 -234 -219 -205 -191 -176 -161 -144 -125 -103 -80 -56 -32 -10 09 27 43 57 70 82 93 103 112 121 129 137 145 7 -1088 -1026 -937 -865 -806 -758 -716 -679 -647 -616 -586 -555 -523 -491 -458 -423 -388 -352 -316 -279 -242 -206 -174 -145 -119 -95 -73 -54 -36 -19 -04 09 22 34 45 55 6 -1717 -1648 -1540 -1440 -1350 -1270 -1196 -1129 -1065 -1005 -948 -892 -839 -787 -737 -687 -639 -591 -543 -496 -449 -405 -365 -328 -295 -265 -238 -214 -191 -171 -152 -135 -119 -104 -90 -78 5 -1948 -1865 -1733 -1609 -1495 -1394 -1303 -1221 -1146 -1077 -1011 -949 -890 -834 -779 -725 -673 -622 -572 -522 -473 -426 -384 -345 -311 -279 -251 -225 -201 -180 -160 -142 -125 -110 -96 -82 4 -1554 -1493 -1399 -1313 -1236 -1165 -1098 -1035 -975 -919 -865 -813 -762 -712 -663 -615 -567 -520 -473 -427 -381 -337 -297 -261 -229 -199 -172 -148 -126 -106 -87 -70 -55 -40 -27 -15 3 -1131 -1078 -993 -916 -852 -798 -752 -712 -674 -637 -600 -563 -526 -489 -452 -414 -375 -336 -297 -258 -218 -181 -146 -115 -88 -62 -39 -19 00 18 34 48 61 74 85 96 2 -169 -161 -149 -137 -125 -113 -101 -90 -78 -67 -55 -44 -33 -22 -11 01 14 30 48 68 90 111 130 148 163 177 190 201 212 221 230 238 245 252 258 263 1 334 336 338 341 344 346 349 351 353 356 358 361 363 365 367 369 372 374 376 379 384 390 395 399 403 407 410 412 414 416 418 419 420 421 422 422 SEGMENT NUM 10 -786 -748 -714 -682 -651 -623 -595 -558 -535 -534 9 -926 -879 -837 -798 -761 -726 -692 -647 -617 -616 8 -1029 -976 -929 -885 -843 -803 -766 -714 -680 -679 7 -1114 -1056 -1006 -958 -913 -870 -829 -773 -736 -734 6 -1240 -1177 -1121 -1069 -1019 -971 -926 -864 -824 -820 5 -1245 -1181 -1126 -1073 -1023 -976 -931 -869 -828 -825 4 -1180 -1120 -1067 -1017 -969 -924 -882 -823 -785 -782 3 -1075 -1020 -972 -926 -882 -841 -802 -748 -714 -712 2 -916 -870 -829 -790 -754 -719 -686 -641 -612 -611 1 -766 -729 -695 -664 -634 -606 -579 -542 -519 -519 ---------------------------------------------------------------------------------------------------- TOTAL STRAIN(AXIAL) (001) IWROD= 14 ---------------------------------------------------------------------------------------------------- SEGMENT NUM 10 1451 1432 1413 1394 1376 1358 1340 1322 1305 1288 1270 1253 1236 1220 1203 1187 1171 1155 1139 1123 1129 1115 1110 1104 1098 1092 1085 1078 1071 1063 1055 1047 1037 1025 1010 982 9 3145 3089 3033 2977 2922 2868 2815 2762 2709 2657 2606 2556 2506 2457 2408 2361 2313 2267 2212 2251 2130 2094 2086 2077 2068 2057 2045 2031 2014 1994 1968 1763 1719 1677 1630 1581 8 4500 4392 4294 4202 4113 4027 3943 3861 3779 3699 3619 3541 3463 3387 3289 3245 3081 2893 2709 2519 2359 2309 2304 2298 2291 2284 2276 2267 2257 2245 2231 2214 2194 2171 2140 2081 7 6183 5744 5439 5218 5048 4909 4786 4674 4567 4505 4337 4167 3988 3802 3603 3398 3201 3004 2803 2599 2429 2374 2371 2367 2363 2358 2353 2346 2339 2331 2321 2309 2294 2276 2252 2220 6 6938 6708 6477 6250 6022 5792 5564 5337 5116 4900 4685 4470 4257 4052 3849 3644 3437 3229 3018 2803 2627 2571 2569 2567 2564 2561 2557 2553 2548 2542 2535 2526 2514 2497 2474 2441 5 6958 6726 6495 6264 6035 5808 5582 5356 5133 4912 4693 4476 4265 4059 3851 3642 3432 3221 3007 2790 2612 2554 2553 2551 2549 2547 2545 2542 2538 2535 2529 2522 2512 2497 2475 2444 4 6826 6593 6364 6134 5903 5667 5425 5195 4979 4769 4558 4344 4128 3915 3708 3502 3294 3085 2874 2658 2481 2422 2421 2420 2417 2414 2411 2408 2404 2400 2394 2387 2376 2362 2342 2314 3 6348 5923 5569 5318 5129 4978 4849 4750 4575 4385 4203 4018 3829 3636 3438 3229 3026 2825 2622 2415 2242 2186 2184 2181
JAEA-DataCode 2013-009
- 212 -
2178 2175 2171 2166 2161 2155 2147 2138 2126 2111 2091 2065 2 3834 3759 3685 3612 3541 3470 3401 3332 3264 3197 3130 3065 3000 2936 2893 2744 2584 2413 2226 2039 1879 1828 1824 1820 1815 1810 1805 1798 1790 1780 1770 1757 1743 1726 1706 1681 1 1865 1837 1809 1782 1755 1728 1702 1676 1650 1625 1600 1575 1550 1526 1502 1478 1455 1431 1468 1355 1234 1196 1192 1188 1183 1179 1174 1168 1162 1156 1150 1142 1135 1127 1118 1108 SEGMENT NUM 10 439 439 439 439 439 439 439 439 439 439 9 347 347 347 347 347 347 347 347 347 347 8 278 278 278 278 278 278 278 278 278 278 7 243 243 243 243 243 243 243 243 243 243 6 208 208 208 208 208 208 208 208 208 208 5 226 226 226 226 226 226 226 226 226 226 4 257 257 257 257 257 257 257 257 257 257 3 297 297 297 297 297 297 297 297 297 297 2 385 385 385 385 385 385 385 385 385 385 1 461 461 461 461 461 461 461 461 461 461 --------------------------------------------------------------------------------------------------------------------- DISPLACEMENT OF NODES (MICRON) GAP IWROD=18 --------------------------------------------------------------------------------------------------------------------- (R-DIRECTION OF Pellet) 10 00 26 37 46 53 59 65 70 75 80 85 89 93 97 101 105 109 112 116 119 122 126 129 132 135 138 141 144 146 149 151 154 156 158 161 163 165 0000 9 00 00 01 02 04 05 07 10 12 14 17 19 22 25 28 31 34 37 40 44 48 52 57 61 65 69 72 76 79 82 86 89 92 95 99 102 105 -0000 8 00 -27 -36 -42 -46 -49 -51 -52 -52 -52 -52 -51 -50 -49 -47 -45 -42 -38 -33 -27 -21 -14 -07 -00 06 12 17 23 28 32 37 41 45 49 53 57 61 -0000 7 00 -74 -95 -107 -114 -119 -123 -126 -128 -129 -130 -129 -128 -125 -121 -117 -111 -104 -97 -89 -80 -70 -61 -52 -44 -36 -29 -22 -16 -10 -04 01 06 11 16 20 25 0000 6 -00 -117 -155 -176 -191 -200 -206 -210 -212 -212 -211 -209 -205 -200 -195 -188 -181 -173 -164 -155 -144 -134 -123 -113 -104 -96 -88 -80 -73 -66 -60 -54 -49 -44 -39 -34 -29 0000 5 00 -133 -175 -198 -212 -221 -226 -228 -229 -228 -226 -222 -218 -212 -206 -199 -191 -183 -173 -163 -152 -141 -130 -119 -110 -101 -92 -84 -77 -70 -63 -57 -51 -46 -41 -36 -31 0000 4 -00 -106 -140 -161 -174 -183 -189 -193 -194 -194 -193 -190 -186 -182 -176 -169 -162 -153 -144 -134 -123 -112 -101 -91 -82 -73 -65 -57 -49 -42 -36 -30 -24 -19 -13 -08 -04 0000 3 00 -77 -100 -113 -121 -126 -130 -132 -134 -134 -134 -132 -129 -125 -120 -115 -108 -100 -92 -83 -73 -62 -52 -43 -34 -25 -18 -10 -03 03 10 16 21 27 32 37 41 0000 2 -00 -12 -15 -17 -18 -18 -18 -17 -16 -15 -13 -11 -09 -07 -04 -02 02 06 11 17 24 32 39 46 52 58 64 70 75 80 84 89 93 97 101 105 109 0000 1 -00 23 33 40 47 53 58 63 68 73 77 81 86 90 94 97 101 105 109 112 116 121 126 130 134 138 142 146 149 153 156 159 162 165 168 171 173 -0000 (R-DIRECTION OF Cladding) 10 -335 -324 -439 -554 -669 -784 -900 -1016 -375 -285 -195 9 -395 -381 -501 -621 -741 -861 -982 -1103 -473 -338 -203 8 -439 -424 -548 -673 -798 -924 -1050 -1176 -557 -381 -204 7 -475 -459 -588 -718 -848 -978 -1109 -1240 -631 -418 -206 6 -529 -511 -648 -786 -924 -1062 -1201 -1340 -747 -477 -207 5 -531 -513 -650 -788 -927 -1065 -1205 -1344 -752 -480 -208 4 -504 -486 -617 -749 -881 -1013 -1146 -1279 -673 -446 -219 3 -459 -443 -566 -690 -813 -938 -1062 -1187 -565 -395 -225 2 -391 -378 -494 -610 -727 -844 -962 -1079 -443 -329 -216 1 -327 -316 -428 -540 -652 -764 -877 -990 -344 -272 -201 (Z-DIRECTION) --------- ----------------- ----------------- SEG NUM PELLET CLADDING --------- ----------------- ----------------- 3320391 (Plenum) 10 17978029 3139636 9 17011908 2700254 8 15111368 2353561 7 13062903 2075618 6 10982308 1832563 5 8725095 1624651 4 6498211 1399123 3 4400908 1142598 2 2524124 845254 1 972470 460646 --------------------------------------------------------------------------------------------------------------------- DISPLACEMENT INCREMENT OF NODES (MICRON) GAP IWROD=18 --------------------------------------------------------------------------------------------------------------------- (R-DIRECTION OF Pellet) 10 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000
JAEA-DataCode 2013-009
- 213 -
9 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -0000 8 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -0000 7 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 6 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 0000 5 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 0000 4 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 0000 3 00 -00 -00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 0000 2 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 0000 1 00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 00 00 00 00 00 00 -0000 (R-DIRECTION OF Cladding) 10 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 9 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 8 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 7 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 -00 6 -00 00 00 00 00 00 00 00 00 00 00 5 00 00 00 00 00 00 00 00 00 00 00 4 00 00 00 00 00 00 00 00 00 00 00 3 00 00 00 00 00 00 00 00 00 00 00 2 00 00 00 00 00 00 00 00 00 00 00 1 00 00 00 00 00 00 00 00 00 00 00 (Z-DIRECTION) --------- ----------------- ----------------- SEG NUM PELLET CLADDING --------- ----------------- ----------------- 0042 (Plenum) 10 0011 0011 9 0014 0014 8 0014 0014 7 0012 0012 6 0008 0008 5 0005 0005 4 0003 0003 3 0005 0005 2 0005 0005 1 0004 0004 STAGE NO 619 PELLET DISPLACEMENT (MICRONS) CLADDING DISPLACEMENT (MICRONS) CLEARANCE CONTACT THERMAL ELASTIC DENSIFI IRRAD RELOC DISPLA THERMAL ELASTIC DISPLA NODE (MICRONS) FORCE(MPA) EXPANS DEFORM CREEP CATION SWELL ATION CEMENT EXPANS DEFORM CREEP CEMENT 10 0000 5970 1265 -090 -869 -2648 2827 1164 1649 822 -138 -3787 -3351 9 -0000 4827 1528 -063 -2705 -2707 3813 1186 1051 851 -177 -4321 -3949 8 -0000 4043 1719 -045 -3905 -2720 4356 1204 609 872 -204 -4717 -4391 7 -0000 3668 1830 -035 -4700 -2725 4659 1217 246 885 -220 -5049 -4754 6 -0000 3224 1911 -024 -5595 -2728 4910 1234 -292 899 -240 -5542 -5292 5 0000 3360 1945 -026 -5704 -2728 4973 1230 -311 900 -239 -5564 -5311 4 0000 3800 1923 -032 -5328 -2728 4914 1216 -036 889 -224 -5313 -5036 3 -0000 4222 1835 -039 -4579 -2725 4710 1211 413 872 -206 -4899 -4587 2 0000 5156 1632 -059 -3115 -2717 4163 1187 1091 847 -171 -4286 -3909 1 -0000 6422 1342 -091 -1190 -2678 3185 1164 1733 817 -122 -3719 -3267 ------------------------------------------------------------------------------------------------------------------- | RESULTS OF THERMAL ANALYSIS THERMAL INFORMATION ( SEGMENT NUMBER 6 ) | ------------------------------------------------------------------------------------------------------------------- ----------------------------------------------------------------------------------------------------------------------------------- P O W E R H I S T O R Y | T H E R M A L I N F O R M A T I O N ----------------------------------------------------------------------------------------------------------------------------------- STEP TIME LINEAR BURNUP | TEMPERATURE GAP CONDUCTANCE RADIAL CONTACT PROD FISS IODN CPU NO HEAT | FUEL FUEL CLAD CLAD TOTAL GAS SOLID BONDING GAP PRESS GAS GAS REL TIME RATE (MWD | CENTER SURFACE INNER OUTER (WCM2 (WCM2 (WCM2 RATIO SIZE (XE+KR) REL (10-5 (HRMSMS) (WCM) TU) | (DEGC)(DEGC)(DEGC)(DEGC) C) C) C) (-) (MIC) (MPA)(10-3MOL)() GCM2)(SEC) ----------------------------------------------------------------------------------------------------------------------------------- 1 0 0 0 0 00 00| 2850 2850 2850 2850 0602 060 000 0000 0 323 00 000 050 0000 0 245 139055442965 3399 292014| 14005 4335 4164 3618 7687 354 006 0667 1 00 94 190 595 2397 12 314 163561451942 12 356537| 2881 2856 2856 2854 6119 123 000 0842 0 55 00 232 775 3809 15 363 198595338887 2316 408858| 10360 3925 3828 3452 9134 282 005 0925 1 00 82 266 755 4256 18 513 283643137758 66 578551| 3054 2887 2883 2872 6939 108 000 1000 0 29 00 377 920 7345 25 |
JAEA-DataCode 2013-009
- 214 -
530 284964457773 1877 579655| 9437 3830 3754 3454 9600 191 002 1000 1 00 53 378 921 7367 26 618 3638551 9574 1214 687736| 7203 3530 3480 3285 9529 125 001 1000 1 00 32 448 1298 12313 30 619 363855730374 1214 687737| 7203 3529 3480 3285 9529 125 001 1000 1 00 32 448 1298 12313 30 ----------------------------------------------------------------------------------------------------------------------------------- ------------------------------------------------------------------------------------------------------------------- | RESULTS OF THERMAL ANALYSIS MECHANICAL INFORMATION ( SEGMENT NUMBER 6 ) | ------------------------------------------------------------------------------------------------------------------- ----------------------------------------------------------------------------------------------------------------------------------- P O W E R H I S T O R Y | F U E L O U T E R S U R F A C E | RADIAL GAP | CLAD INNER SURFACE ----------------------------------------------------------------------------------------------------------------------------------- STEP TIME LINEAR BURNUP | THERMAL CREEP DENSIFI SWELL RELOCA RADIAL | RAD CONTACT|THERMAL ELASTIC CREEP RADIAL NO HEAT | EXPAN -CATION -ING -TION DISPLA | GAP PRESS | EXPAN DEFORM DISPLA RATE (MWD | -SION -CEMENT | | -SION -ATION -CEMENT (HRMSMS) (WCM) TU) | (MIC) (MIC) (MIC) (MIC) (MIC) (MIC) | (MIC) (MPA)| (MIC) (MIC) (MIC) (MIC) ----------------------------------------------------------------------------------------------------------------------------------- 1 0 0 0 0 00 00| 729 000 000 000 1345 2074 | 323 00 | 734 -407 000 306 245 139055442965 3399 292014| 4556 -3814 -2564 2344 1140 1471 | 00 94 | 1070 -093 -4200 -3529 314 163561451942 12 356537| 737 -4304 -2639 2835 2962 -222 | 55 00 | 735 -332 -4725 -4671 363 198595338887 2316 408858| 2983 -4067 -2674 3241 1143 467 | 00 82 | 985 -107 -5049 -4533 513 283643137758 66 578551| 777 -5410 -2720 4406 2290 -546 | 29 00 | 742 -342 -5260 -5252 | | | 530 284964457773 1877 579655| 2665 -5407 -2720 4413 1199 105 | 00 53 | 969 -213 -5264 -4895 618 3638551 9574 1214 687736| 1911 -5595 -2728 4910 1234 -292 | 00 32 | 899 -240 -5541 -5292 619 363855730374 1214 687737| 1911 -5595 -2728 4910 1234 -292 | 00 32 | 899 -240 -5542 -5292 ----------------------------------------------------------------------------------------------------------------------------------- ------------------------------------------------------------------------------------------------------------------- | RESULTS OF THERMAL ANALYSIS FISSION GAS INFORMATION ( SEGMENT NUMBER 6 ) | ------------------------------------------------------------------------------------------------------------------- ----------------------------------------------------------------------------------------------------------------------------------- P O W E R H I S T O R Y | F U E L C E N T E R | | F U E L - C L A D ----------------------------------------------------------------------------------------------------------------------------------- STEP TIME LINEAR BURNUP | FUEL GRAIN BUBBLE BUBBLE DIFFUS DIFFUS GAS SATURA | LOCAL |FISSON AMOUNT XE+KR NO HEAT | CENTER RADIUS RADIUS DENSITY COEFF COEFF DENSAT -TION | FGR AT| GAS OF GAS IN GAP RATE (MWD | TEMP (10D14 EFFECT BOUND DENS | CENTER| REL IN GAP (HRMSMS) (WCM) TU) | (DEGC) (MIC) (ANGST) BCM3) (10D-16 CM2S) (10D13 ATCM2) | () | () (10-3MOL) () ----------------------------------------------------------------------------------------------------------------------------------- 1 0 0 0 0 00 00| 2850 50 00 193532 02 02 00 2610 | 050 | 050 009 000 245 139055442965 3399 292014| 14005 53 114 42205 454 298 2317 2317 | 5579 | 595 003 999 314 163561451942 12 356537| 2881 54 22 130136 02 02 438 2811 | 6489 | 775 008 1504 363 198595338887 2316 408858| 10360 54 28 119001 03 03 563 2368 | 5712 | 755 004 1611 513 283643137758 66 578551| 3054 54 33 109726 02 02 1074 3047 | 4151 | 920 008 2948 | | | 530 284964457773 1877 579655| 9437 54 33 109523 02 02 978 1806 | 4144 | 921 005 2956 618 3638551 9574 1214 687736| 7203 54 37 103495 02 02 1080 2151 | 3549 | 1298 007 4451 619 363855730374 1214 687737| 7203 54 37 103495 02 02 1080 2151 | 3549 | 1298 007 4451 ----------------------------------------------------------------------------------------------------------------------------------- ------------------------------------------------------------------------------------------------------------------- | RESULTS OF THERMAL ANALYSIS FISSION GAS INFORMATION ( WHOLE FUEL ROD ) | ------------------------------------------------------------------------------------------------------------------- ----------------------------------------------------------------------------------------------------------------------------------- P O W E R H I S T O R Y | F U E L R O D ----------------------------------------------------------------------------------------------------------------------------------- STEP TIME LINEAR BURNUP | AMOUNT OF GAS FRACTION OF GAS MIXTURE FISSION INNER NO HEAT | PRODUCE RELEASE PLENUM GAP TOTAL IN GAS GAS RATE (MWD (10D20 | (XE+KR) (XE+KR) FUEL ROD HE N2 KR XE RELEASE PRESS (HRMSMS) (WCM) TU) FISSCC)| (10D-3 MOLE) () () () () () (MPA) ----------------------------------------------------------------------------------------------------------------------------------- 1 0 0 0 0 00 00 000 | 000 000 324 090 414 10000 000 000 000 050 194 245 139055442965 3399 235664 582 | 1535 044 391 040 432 9587 000 131 878 284 249 314 163561451942 12 288442 713 | 1879 069 379 077 457 9070 000 197 1315 368 228 363 198595338887 2316 332016 821 | 2163 075 401 048 449 9232 000 217 1449 346 258 513 283643137758 66 479942 1186 | 3127 158 440 089 530 7853 000 389 2602 507 286 | 530 284964457773 1877 480941 1189 | 3133 159 465 055 520 8002 000 398 2661 507 308 618 3638551 9574 1214 578801 1431 | 3771 300 575 080 655 6390 000 595 3983 795 387 619 363855730374 1214 578802 1431 | 3771 300 575 080 655 6390 000 595 3983 795 387 ----------------------------------------------------------------------------------------------------------------------------------- ------------------------------------------------------------------------------------------------------------------- | RESULTS OF FEM MECHANICAL ANALYSIS FUEL AND CLAD DEFORMATIONS ( ANALYZED SEGMENT NUMBER 6 ) | ------------------------------------------------------------------------------------------------------------------- ----------------------------------------------------------------------------------------------------------------------------------- P O W E R H I S T O R Y | DIAMETRAL FUEL TOP | DIAMETRAL GAP | DIAMETRAL CLADDING | DIA RIDGE ----------------------------------------------------------------------------------------------------------------------------------- STEP TIME LINEAR BURNUP | AXIAL AXIAL RADIAL RADIAL| RADIAL CONTACT CONTACT| AXIAL RADIAL RADIAL | RIDGE RIDGE NO HEAT | DIPS DIPS DIPS DIPS | GAP AT PRESS PRESS | DISP DISP DISP |HEIGHT HEIGHT RATE (MWD | CENTER SURF INNER OUTER | TOP AXIAL RADIAL | AT TOP OUTTOP OUTMID| MAX TOP-MID (HRMSMS) (WCM) TU) | (MM) (MM) (MIC) (MIC) | (MIC) (MPA) (MPA) | (MM) (MIC) (MIC) | (MIC) (MIC) ----------------------------------------------------------------------------------------------------------------------------------- 1 0 0 0 0 00 00| 5414 5414 00 415 | 646 00 00 | 0773 93 93 | 00 00 245 139055442965 3399 292014| 8360 8360 00 294 | 00 13 94 | 2905 -394 -394 | 00 00 314 163561451942 12 356537| 7785 7785 00 -44 | 110 00 00 | 2647 -556 -556 | 00 00 363 198595338887 2316 408858| 10858 10858 00 93 | -00 07 82 | 2880 -490 -490 | 00 00 513 283643137758 66 578551| 14128 14128 00 -109 | 59 00 00 | 2986 -494 -494 | 00 00 | | | | 530 284964457773 1877 579655| 15224 15224 -00 21 | 00 08 53 | 3149 -418 -418 | 00 00 618 3638551 9574 1214 687736| 17978 17978 -00 -58 | -00 05 32 | 3320 -415 -415 | 00 00
JAEA-DataCode 2013-009
- 215 -
619 363855730374 1214 687737| 17978 17978 -00 -58 | -00 05 32 | 3320 -414 -414 | 00 00 ----------------------------------------------------------------------------------------------------------------------------------- ------------------------------------------------------------------------------------------------------------------- | RESULTS OF FEM MECHANICAL ANALYSIS STRESSES AND STRAINS IN FUEL ( ANALYZED SEGMENT NUMBER 6 ) | ------------------------------------------------------------------------------------------------------------------- ----------------------------------------------------------------------------------------------------------------------------------- P O W E R H I S T O R Y | T O P A N D I N N E R O F F U E L ----------------------------------------------------------------------------------------------------------------------------------- STEP TIME LINEAR BURNUP | CIRCUM AXIAL RADIAL CIRCUM AXIAL RADIAL EQUIV EQUIV CIRCUM AXIAL RADIAL EQUIV NO HEAT | TOTAL TOTAL TOTAL CREEP CREEP CREEP CREEP PLAST STRESS STRESS STRESS STRESS RATE (MWD | STRAIN STRAIN STRAIN STRAIN STRAIN STRAIN STRAIN STRAIN (HRMSMS) (WCM) TU) |(001) (001) (001) (001)(001)(001)(001)(001) (MPA) (MPA) (MPA) (MPA) ----------------------------------------------------------------------------------------------------------------------------------- 1 0 0 0 0 00 00| 51 68 51 0 -0 0 0 0 00 -00 00 00 245 139055442965 3399 292014| -24 563 -24 -208 364 -208 381 0 -67 -64 -67 14 314 163561451942 12 356537| -135 556 -135 -249 407 -249 437 0 118 154 118 36 363 198595338887 2316 408858| -106 561 -106 -244 398 -244 428 0 -65 -00 -65 65 513 283643137758 66 578551| -173 656 -173 -300 499 -300 533 0 68 96 68 28 | 530 284964457773 1877 579655| -143 671 -143 -300 499 -300 533 0 -12 -14 -12 04 618 3638551 9574 1214 687736| -172 694 -172 -314 526 -314 560 0 -05 18 -05 23 619 363855730374 1214 687737| -172 694 -172 -314 526 -314 560 0 -05 18 -05 23 ----------------------------------------------------------------------------------------------------------------------------------- ------------------------------------------------------------------------------------------------------------------- | RESULTS OF FEM MECHANICAL ANALYSIS STRESSES AND STRAINS IN CLAD ( ANALYZED SEGMENT NUMBER 6 ) | ------------------------------------------------------------------------------------------------------------------- ----------------------------------------------------------------------------------------------------------------------------------- P O W E R H I S T O R Y | T O P A N D I N N E R O F C L A D D I N G ----------------------------------------------------------------------------------------------------------------------------------- STEP TIME LINEAR BURNUP | CIRCUM AXIAL RADIAL CIRCUM AXIAL RADIAL EQUIV EQUIV CIRCUM AXIAL RADIAL EQUIV NO HEAT | TOTAL TOTAL TOTAL CREEP CREEP CREEP CREEP PLAST STRESS STRESS STRESS STRESS RATE (MWD | STRAIN STRAIN STRAIN STRAIN STRAIN STRAIN STRAIN STRAIN (HRMSMS) (WCM) TU) |(001) (001) (001) (001)(001)(001)(001)(001) (MPA) (MPA) (MPA) (MPA) ----------------------------------------------------------------------------------------------------------------------------------- 1 0 0 0 0 00 00| 8 8 24 -0 0 0 0 0 -997 -519 -49 821 245 139055442965 3399 292014| -78 21 155 -101 -26 128 135 0 -339 -348 -124 220 314 163561451942 12 356537| -104 16 169 -114 -33 147 154 0 -792 -360 -44 650 363 198595338887 2316 408858| -101 18 182 -122 -34 156 164 0 -386 -411 -115 284 513 283643137758 66 578551| -117 17 191 -127 -42 169 176 0 -836 -428 -51 680 | 530 284964457773 1877 579655| -109 20 195 -127 -42 169 176 0 -560 -368 -97 403 618 3638551 9574 1214 687736| -118 21 203 -134 -44 177 185 0 -639 -436 -87 484 619 363855730374 1214 687737| -118 21 203 -134 -44 177 185 0 -639 -436 -87 484 ----------------------------------------------------------------------------------------------------------------------------------- ------------------------------------------------------------------------------------------------------------------- | RESULTS OF FEM MECHANICAL ANALYSIS FUEL AND CLAD DEFORMATIONS ( WHOLE FUEL ROD ) | | AND THERMAL ANALYSIS FUEL FREE VOLUME AND CLADDING OXIDATION INFORMATION | ------------------------------------------------------------------------------------------------------------------- ----------------------------------------------------------------------------------------------------------------------------------- P O W E R H I S T O R Y | F U E L R O D | OXIDE THICKNESS ----------------------------------------------------------------------------------------------------------------------------------- STEP TIME LINEAR BURNUP FLUEN | CLAD FUEL CLAD INNER FUEL PLENUM | OXIDE OXIDE NO HEAT CE(10 | DIA AXIAL AXIAL GAS FREE VOLUME | THICK THICK RATE (MWD (MWDT) E19N | DISP DISP DISP PRESSURE VOLUME | AVE MAX (HRMSMS) (WCM) TUO2) CM2) | (MIC) (001) (001) (MPA) (CM3) (CM3) | (MIC) (MIC) ----------------------------------------------------------------------------------------------------------------------------------- 1 0 0 0 0 00 00 00 00 | 933 5414 673 1938 9908 7749 | 0100 0100 245 139055442965 2773 207733 235664 6137 | -3957 8360 2531 2493 9031 7705 | 11180 16267 314 163561451942 10 254256 288442 7483 | -5276 7785 2306 2280 9303 7722 | 14973 22739 363 198595338887 1943 292666 332016 8592 | -4666 10858 2509 2584 8906 7568 | 17212 26062 513 283643137758 60 423060 479942 12145 | -4913 14128 2601 2863 8871 7397 | 28099 44001 | | 530 284964457773 1699 423941 480941 12169 | -4196 15224 2743 3082 8601 7347 | 28163 44092 618 3638551 9574 1100 510203 578801 14427 | -4169 17978 2893 3869 8502 7207 | 34844 54478 619 363855730374 1100 510203 578802 14428 | -4167 17978 2893 3869 8502 7207 | 34844 54479 ----------------------------------------------------------------------------------------------------------------------------------- INS1M= 0 INS2M= 0 INS3M= 0 ----------------------------- --- Calculation completed --- -----------------------------
72 Plotting control data file image of ldquoexplotABCrdquo
Sample Case Plotting Control
16
101
63018 Average LHR
JAEA-DataCode 2013-009
- 216 -
1
1
12000
5155620513
00600513
301
6301646464 Fast Flux
111
357
12000
5155620513
00600513
301
6301535353 Pellet center temperature
111
357
12000
5155620513
00600513
301
6301545454 Pellet surface temperature
101010
357
12000
5155620513
00600513
101
63012 Fission Gas Relase Rate
1
2
12000
5155620513
00600513
101
63013 Rod Internal Pressure
1
1
12000
5155620513
351050513
301
6301676767 Gap width
111
357
JAEA-DataCode 2013-009
- 217 -
12000
5155620513
00600513
301
6301494949 Gap Conductance
111
357
12000
5155620513
00600513
301
6301787878 Cladding Outer surface Diameter change
111
357
12000
5155620513
00600513
301
6301154154154 Cladding Hoop Stress
555
357
12000
7180724010-13
00600513
301
6301818181 Pellet Diameter change
111
357
12000
5155620513
00600513
311
2331101101101 Pellet local burnup
111
555
10 15200
5155620513
00600513
101
63016 Cladding Average elongation
1
1
12000
5155620513
JAEA-DataCode 2013-009
- 218 -
020800523
301
6301525252 Clad outer temperature
111
357
12000
5155620513
00600513
301
6301505050 Coolant temperature
111
1510
12000
5155620513
00600513
301
6301595959 Oxide thickness
111
357
1 1000
5155620513
00600513
73 Images of plotted output ldquoABC1ABCpdfrdquo
JAEA-DataCode 2013-009
- 219 -
JAEA-DataCode 2013-009
- 220 -
JAEA-DataCode 2013-009
- 221 -
JAEA-DataCode 2013-009
- 222 -
JAEA-DataCode 2013-009
- 223 -
JAEA-DataCode 2013-009
- 224 -
74 Example of numerical output of HBS model The result file which is generated by the High burnup structure formation model has a format of the ASCII table so as to be read by EXCEL or other gpaphical plotting softwares A sample of this file is presented in Figs 741 (12) and (22) Time Step No 431 time(hr)= 4807920 Segment No 1 2 3 4 5 6 7 8 9 10 11 12 Burnup(MWdt) 66214 247436 345140 407444 451814 472564 479751 481165 444920 399073 311228 114811 Power(Wcm) 47 47 47 47 47 47 47 47 47 47 47 47 Pellet Radius(cm) Local Burnup (MWdtU) 02600 59535 223747 312851 369954 410759 429871 436494 437799 404413 362269 281870 103406 06277 59535 223747 312851 369954 410759 429871 436494 437799 404413 362269 281870 103406 08180 59535 223747 312851 369954 410759 429871 436494 437799 404414 362269 281870 103406
51346 89214 369653 529193 630008 699531 731078 741868 743986 688916 616560 473792 161066 51608 90464 379943 546566 651956 724293 756951 768099 770286 713281 637905 488643 164049 51870 91755 390889 565226 675618 751010 784867 796398 798661 739569 660907 504550 167162 Pellet Radius(cm) Effective Burnup (GWdtU) 02600 5953 22374 16846 11614 4517 4131 4261 4698 5208 10668 21238 10340 06277 5953 22374 16901 12376 4782 4145 4279 4782 5305 12739 21263 10340 08180 5953 22374 16962 13210 5135 4161 4298 4865 5422 15584 21292 10340
51346 8921 36964 52917 62998 69950 73105 74184 74395 68889 61653 47377 16106 51608 9046 37993 54654 65193 72426 75692 76806 77025 71325 63788 48862 16404 51870 9175 39087 56520 67559 75098 78483 79636 79863 73954 66088 50453 16715
Pellet Radius(cm) Pellet Temperature (C) 00000 2970 2933 2924 2945 2984 3040 3100 3155 3183 3193 3201 3254 05200 2970 2932 2924 2944 2983 3039 3099 3154 3182 3192 3200 3253 07354 2969 2932 2923 2943 2982 3038 3098 3153 3181 3192 3200 3253
51477 2925 2870 2853 2867 2902 2956 3015 3070 3101 3116 3132 3204 51739 2925 2870 2852 2866 2901 2954 3014 3069 3100 3115 3131 3203 52000 2924 2869 2851 2865 2899 2953 3013 3067 3099 3114 3130 3203 Pellet Radius(cm) Pellet Thermal Conductivity (WcmK) 02600 07561 05572 04876 04514 04286 04185 04150 04142 04312 04549 05082 06871 06277 07561 05572 04876 04514 04286 04185 04150 04142 04312 04549 05082 06871 08180 07561 05572 04876 04514 04286 04185 04150 04142 04312 04549 05083 06871
50550 07158 04685 03935 03574 03359 03268 03237 03231 03386 03612 04156 06263 51608 07089 04459 03676 03308 03127 03102 03104 03104 03142 03347 03906 06139 51870 07070 04398 03605 03237 03104 03119 03134 03137 03107 03275 03838 06106
Fig741 (12) Example of HBS model output (ft17d)
JAEA-DataCode 2013-009
- 225 -
Pellet Radius(cm) Pellet Porosity () 02600 300 300 300 300 300 300 300 300 300 300 300 300 06277 300 300 300 300 300 300 300 300 300 300 300 300 08180 300 300 300 300 300 300 300 300 300 300 300 300
51346 300 300 300 300 302 313 321 323 301 300 300 300 51608 300 300 300 300 309 338 356 360 305 300 300 300 51870 300 300 300 300 331 391 423 430 319 300 300 300 Pellet Radius(cm) Pellet xv ratio () 02600 00 00 00 00 00 00 00 00 00 00 00 00 06277 00 00 00 00 00 00 00 00 00 00 00 00 08180 00 00 00 00 00 00 00 00 00 00 00 00
50281 00 00 00 00 00 00 00 00 00 00 00 00 50550 00 00 00 00 00 03 13 17 00 00 00 00 50816 00 00 00 00 00 39 84 96 00 00 00 00 51082 00 00 00 00 17 171 281 307 04 00 00 00 51346 00 00 00 00 112 481 692 739 54 00 00 00 51608 00 00 00 00 372 1070 1413 1487 232 00 00 00 51870 00 00 00 16 909 2031 2520 2621 643 01 00 00 Pellet Radius(cm) Fission Gas Release ratio () 02600 50 50 50 50 50 165 215 221 50 50 50 50 06277 50 50 50 50 50 149 193 200 50 50 50 50 08180 50 50 50 50 50 146 190 197 50 50 50 50
50281 50 50 50 50 50 50 50 50 50 50 50 50 50550 50 50 50 50 50 50 50 50 50 50 50 50 50816 50 50 50 50 50 907 906 911 50 50 50 50 51082 50 50 50 50 752 1018 1090 1104 50 50 50 50 51346 50 50 50 50 806 1018 1090 1104 646 50 50 50 51608 50 50 50 50 806 1018 1090 1104 735 50 50 50 51870 50 50 50 50 806 1018 1090 1104 735 50 50 50
Fig741 (22) Example of HBS model output (ft17d)
JAEA-DataCode 2013-009
- 226 -
75 Sample inputoutput of RODBURN-1
(1) input data file ABCrddat PWR-type Rod Sample Case (May 2011) 1 10 -2 36 1 1 0 0 1 0 1 1 4 0 100000 0000 0820 0970 1600 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 127315 77315 61315 59315 09500 00000 09600 00400 22 0670 0935 1081 1242 1286 1257 1086 1006 0850 0585 0676 0936 1111 1227 1267 1238 1100 1001 0849 0594 0678 0937 1120 1222 1260 1232 1105 0999 0849 0597 0679 0937 1130 1217 1254 1226 1109 0998 0849 0600 0680 0938 1136 1214 1250 1222 1112 0997 0849 0602 0681 0938 1139 1212 1248 1220 1114 0996 0848 0603 0681 0938 1140 1212 1247 1219 1114 0996 0848 0603 0681 0938 1140 1212 1247 1219 1114 0996 0848 0603 0681 0938 1140 1212 1247 1219 1114 0996 0849 0603 0709 0953 1132 1192 1218 1192 1108 1005 0864 0628 0739 0970 1123 1171 1185 1162 1100 1014 0880 0655 0751 0976 1119 1162 1173 1151 1098 1018 0887 0666 0775 0990 1112 1145 1147 1127 1092 1025 0900 0687 0792 0999 1106 1133 1129 1110 1088 1031 0909 0703 0798 1002 1104 1128 1123 1104 1086 1032 0912 0708 0798 1002 1104 1128 1122 1104 1086 1032 0912 0708 0798 1002 1104 1128 1122 1104 1086 1032 0912 0708 0798 1002 1104 1128 1122 1104 1086 1032 0912 0708 0798 1002 1104 1128 1122 1104 1086 1032 0912 0708 0798 1002 1104 1128 1122 1104 1086 1032 0912 0708 0798 1002 1104 1128 1122 1104 1086 1032 0912 0708 0798 1002 1104 1128 1122 1104 1086 1032 0912 0708 22 2000 010
JAEA-DataCode 2013-009
- 227 -
0846831 1 001 10591 399605366 2 10805 23591 492838987 3 23746 25646 579413064 4 25814 27726 631357510 5 27834 25914 667947308 6 25981 25019 681414387 7 25035 9629 681510390 8 9629 096 682374416 9 096 9629 827495656 10 9714 19427 942927758 11 19615 21577 988026812 12 21660 20675 1081485092 13 20833 20337 1155127851 14 20453 18956 1181334058 15 18992 17992 1181855365 16 17993 600 1187364624 17 600 16993 1242897959 18 16993 15994 1336733088 19 15994 14994 1403604099 20 14994 13994 1516077261 21 13994 10996 1516081668 22 10996 10996 1 758041 3 1 2 3 4 5 6 7 8 9 10 STOP
(2) Output file ABCrdout ==================================================================================================================================
==
==================================================================================================================================
==================================================================================================================================
RRRRRRRR BBBBBBBB 111
RR RR BB BB 1111
RR RR BB BB 11
RR RR BB BB 11
RRRRRRRR BBBBBBBB 11
RRRR BB BB 11
RR RR BB BB 11
RR RR BB BB 11
RR RR BBBBBBBB 111111
==================================================================================================================================
==================================================================================================================================
RODBURN PWR-type Rod Sample Case (May 2011) VERSION 12 (Septembar 2005)
INPUT FILECFEM_ranwrkABCd RUN DATE11MAY12 START TIME144735
IPRIN(1)= 6
I N P U T D A T A L I S T
-------------------------------
1 2 3 4 5 6 7 8
CARD NO 5050505050505050
1 PWR-type Rod Sample Case (May 2011)
2 1 10 -2 36 1 1 0 0 1 0
3 1 1 4 0
4 100000 0000 0820 0970 1600
5 10000 10000 10000 10000 10000 10000 10000 10000 10000
6 10000
7 127315 77315 61315 59315
8 09500 00000
9 09600 00400
10 22
JAEA-DataCode 2013-009
- 228 -
11 0670 0935 1081 1242 1286 1257 1086 1006 0850
12 0585
13 0676 0936 1111 1227 1267 1238 1100 1001 0849
14 0594
15 0678 0937 1120 1222 1260 1232 1105 0999 0849
16 0597
17 0679 0937 1130 1217 1254 1226 1109 0998 0849
18 0600
19 0680 0938 1136 1214 1250 1222 1112 0997 0849
20 0602
21 0681 0938 1139 1212 1248 1220 1114 0996 0848
22 0603
23 0681 0938 1140 1212 1247 1219 1114 0996 0848
24 0603
25 0681 0938 1140 1212 1247 1219 1114 0996 0848
26 0603
27 0681 0938 1140 1212 1247 1219 1114 0996 0849
28 0603
29 0709 0953 1132 1192 1218 1192 1108 1005 0864
30 0628
31 0739 0970 1123 1171 1185 1162 1100 1014 0880
32 0655
33 0751 0976 1119 1162 1173 1151 1098 1018 0887
34 0666
35 0775 0990 1112 1145 1147 1127 1092 1025 0900
36 0687
37 0792 0999 1106 1133 1129 1110 1088 1031 0909
38 0703
39 0798 1002 1104 1128 1123 1104 1086 1032 0912
40 0708
41 0798 1002 1104 1128 1122 1104 1086 1032 0912
42 0708
43 0798 1002 1104 1128 1122 1104 1086 1032 0912
44 0708
45 0798 1002 1104 1128 1122 1104 1086 1032 0912
46 0708
47 0798 1002 1104 1128 1122 1104 1086 1032 0912
48 0708
49 0798 1002 1104 1128 1122 1104 1086 1032 0912
50 0708
5050505050505050
RODBURN PWR-type Rod Sample Case (May 2011) VERSION 12
I N P U T D A T A L I S T
-------------------------------
1 2 3 4 5 6 7 8
CARD NO 5050505050505050
51 0798 1002 1104 1128 1122 1104 1086 1032 0912
52 0708
53 0798 1002 1104 1128 1122 1104 1086 1032 0912
54 0708
55 22 2000 010
56 0846831 1 001 10591
57 399605366 2 10805 23591
58 492838987 3 23746 25646
59 579413064 4 25814 27726
60 631357510 5 27834 25914
61 667947308 6 25981 25019
62 681414387 7 25035 9629
63 681510390 8 9629 096
64 682374416 9 096 9629
65 827495656 10 9714 19427
66 942927758 11 19615 21577
67 988026812 12 21660 20675
68 1081485092 13 20833 20337
69 1155127851 14 20453 18956
70 1181334058 15 18992 17992
71 1181855365 16 17993 600
72 1187364624 17 600 16993
73 1242897959 18 16993 15994
74 1336733088 19 15994 14994
75 1403604099 20 14994 13994
76 1516077261 21 13994 10996
JAEA-DataCode 2013-009
- 229 -
77 1516081668 22 10996 10996
78 1
79 758041
80 3
81 1 2 3 4 5 6 7 8 9 10
82 STOP
5050505050505050
RODBURN PWR-type Rod Sample Case (May 2011) VERSION 12
PWR-type Rod Sample Case (May 2011)
CONTROL DATA
1 MODEL =1PWR =2BWR =3HWR =4PWR(MOX) =5BWR(MOX)
10 MESHZ NUMBER OF AXIAL MESHES(=lt 40)
-2 KREG1 NUMBER OF RADIAL MESHES(=lt 39)
36 MESHR NUMBER OF PELLET RADIAL MESHES(=lt 36)
1 IOPT POWER HISTORY DATA OPTION (0INPUT AVERAGE THERMAL FLUX)
(1INPUT AVERAGE POWER DENSITY (WCM))
1 IDIST AXIAL DISTRIBUTION INPUT OPTION(0COSINE1INPUT)
0 MODEL2 =1PWR =2BWR =3HWR =4PWR(MOX) =5BWR(MOX)
0 KREG2 NUMBER OF RADIAL MESHES FOR MODEL2(=lt 39)
(0DOES NOT CALCULATE BY RABBLE)
1 IFLPW =0AXIAL FLUX DISTRIBUTION =1AXIAL POWER DISTRIBUTION
0 ISTOP =0NOMAL CALCULATION =1INPUT DATA CHECK
SPECTRAL INDICES
THERM = 07010 RES = 03040 FAST = 20100
CONTROL DATA 2
1 IAUTO =0NUCLIDE NUM amp CONC INPUT =1AUTO GENERATE
1 IPTCH1 =0BOUNDARY DIAMETER INPUT =1FUEL ROD PITCH INPUT
4 IZR1 =2ZIRCALOY-2 =4ZIRCALOY-4
0 IHD1 =0H2O(COOLANT) =1D2O(COOLANT)
0 IPTCH2 =0BOUNDARY DIAMETER INPUT =1FUEL ROD PITCH INPUT
0 IZR2 =2ZIRCALOY-2 =4ZIRCALOY-4
0 IHD2 =0H2O(COOLANT) =1D2O(COOLANT)
FUEL PIN SIZE
1000000 ZLENG FUEL ACTIVE LENGTH (CM)
00000 PDIN PELLET INNER DIAMETER (CM)
08200 PDIA PELLET OUTER DIAMETER (CM)
09700 CDOUT1 CLADDING OUTER DIAMETER (CM)
16000 PITCH1 FUEL ROD PITCH (CM)
00000 CDOUT2 CLADDING OUTER DIAMETER (CM)
00000 PITCH2 FUEL ROD PITCH (CM)
AXIAL DISTANCE FOR EACH MESH(CM)
1000E+01 2000E+01 3000E+01 4000E+01 5000E+01 6000E+01 7000E+01 8000E+01 9000E+01 1000E+02
RADIAL DISTANCE FOR EACH MESH(CM)
0000E+00 6833E-02 9664E-02 1184E-01 1367E-01 1528E-01 1674E-01 1808E-01 1933E-01 2050E-01 2161E-01 2266E-01
2367E-01 2464E-01 2557E-01 2647E-01 2733E-01 2817E-01 2899E-01 2979E-01 3056E-01 3131E-01 3205E-01 3277E-01
3348E-01 3417E-01 3484E-01 3551E-01 3616E-01 3680E-01 3743E-01 3805E-01 3866E-01 3925E-01 3984E-01 4043E-01
4100E-01
FUEL MATRIALS(1)
09500 FDEN FUEL FRACTIONAL DENSITY (-)
00000 FPUO2 PUO2 WEIGHT FRACTION (WT FRAC)
FUEL MATRIALS(2)
09600 FU238 U238U-TOTAL (WT FRAC)
00400 FU235 U235U-TOTAL (WT FRAC)
00000 FU232 U232U-TOTAL (WT FRAC)
JAEA-DataCode 2013-009
- 230 -
00000 FU233 U233U-TOTAL (WT FRAC)
00000 FU234 U234U-TOTAL (WT FRAC)
00000 FU236 U236U-TOTAL (WT FRAC)
00000 FU237 U237U-TOTAL (WT FRAC)
00000 FU239 U239U-TOTAL (WT FRAC)
00000 FU240 U240U-TOTAL (WT FRAC)
NUCLIDE NUMBER AND CONCENTRATION(GCC)
MIXTURE NO NUCLIDE CONCENTRATION
1 U238 8810E+00
1 U235 3671E-01
1 O 1235E+00
2 ZR-4 6550E+00
3 H 7900E-02
3 O 6310E-01
ARRAY DESCRIPTION OF MIXTURE
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 3 3
VOLUME(CM3) OF FUEL SEGMENT
RADIAL
AXIAL 1 2 3 4 5 6 7 8 9 10
1 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
2 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
3 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
4 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
5 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
6 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
7 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
8 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
9 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
10 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
RADIAL
AXIAL 11 12 13 14 15 16 17 18 19 20
1 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
2 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
3 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
4 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
5 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
6 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
7 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
8 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
9 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
10 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
RADIAL
AXIAL 21 22 23 24 25 26 27 28 29 30
1 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
2 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
3 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
4 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
5 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
6 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
7 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
8 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
9 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
10 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01 1467E-01
FUEL PELLET TOTAL WEIGHT (GRAM) = 549859
JAEA-DataCode 2013-009
- 231 -
NUMBER OF PATTERNS FOR AXIAL FLUX DISTRIBUTION NDIST = 22
INPUT AXIAL POWER DISTRIBUTION
1 6700E-01 9350E-01 1081E+00 1242E+00 1286E+00 1257E+00 1086E+00 1006E+00 8500E-01 5850E-01
2 6760E-01 9360E-01 1111E+00 1227E+00 1267E+00 1238E+00 1100E+00 1001E+00 8490E-01 5940E-01
3 6780E-01 9370E-01 1120E+00 1222E+00 1260E+00 1232E+00 1105E+00 9990E-01 8490E-01 5970E-01
4 6790E-01 9370E-01 1130E+00 1217E+00 1254E+00 1226E+00 1109E+00 9980E-01 8490E-01 6000E-01
5 6800E-01 9380E-01 1136E+00 1214E+00 1250E+00 1222E+00 1112E+00 9970E-01 8490E-01 6020E-01
6 6810E-01 9380E-01 1139E+00 1212E+00 1248E+00 1220E+00 1114E+00 9960E-01 8480E-01 6030E-01
7 6810E-01 9380E-01 1140E+00 1212E+00 1247E+00 1219E+00 1114E+00 9960E-01 8480E-01 6030E-01
8 6810E-01 9380E-01 1140E+00 1212E+00 1247E+00 1219E+00 1114E+00 9960E-01 8480E-01 6030E-01
9 6810E-01 9380E-01 1140E+00 1212E+00 1247E+00 1219E+00 1114E+00 9960E-01 8490E-01 6030E-01
10 7090E-01 9530E-01 1132E+00 1192E+00 1218E+00 1192E+00 1108E+00 1005E+00 8640E-01 6280E-01
11 7390E-01 9700E-01 1123E+00 1171E+00 1185E+00 1162E+00 1100E+00 1014E+00 8800E-01 6550E-01
12 7510E-01 9760E-01 1119E+00 1162E+00 1173E+00 1151E+00 1098E+00 1018E+00 8870E-01 6660E-01
13 7750E-01 9900E-01 1112E+00 1145E+00 1147E+00 1127E+00 1092E+00 1025E+00 9000E-01 6870E-01
14 7920E-01 9990E-01 1106E+00 1133E+00 1129E+00 1110E+00 1088E+00 1031E+00 9090E-01 7030E-01
15 7980E-01 1002E+00 1104E+00 1128E+00 1123E+00 1104E+00 1086E+00 1032E+00 9120E-01 7080E-01
16 7980E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9120E-01 7080E-01
17 7980E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9120E-01 7080E-01
18 7980E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9120E-01 7080E-01
19 7980E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9120E-01 7080E-01
20 7980E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9120E-01 7080E-01
21 7980E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9120E-01 7080E-01
22 7980E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9120E-01 7080E-01
NORMALIZED POWER DISTRIBUTION
1 6701E-01 9352E-01 1081E+00 1242E+00 1286E+00 1257E+00 1086E+00 1006E+00 8502E-01 5851E-01
2 6761E-01 9361E-01 1111E+00 1227E+00 1267E+00 1238E+00 1100E+00 1001E+00 8491E-01 5941E-01
3 6781E-01 9371E-01 1120E+00 1222E+00 1260E+00 1232E+00 1105E+00 9991E-01 8491E-01 5971E-01
4 6791E-01 9371E-01 1130E+00 1217E+00 1254E+00 1226E+00 1109E+00 9981E-01 8491E-01 6001E-01
5 6800E-01 9380E-01 1136E+00 1214E+00 1250E+00 1222E+00 1112E+00 9970E-01 8490E-01 6020E-01
6 6811E-01 9381E-01 1139E+00 1212E+00 1248E+00 1220E+00 1114E+00 9961E-01 8481E-01 6031E-01
7 6811E-01 9382E-01 1140E+00 1212E+00 1247E+00 1219E+00 1114E+00 9962E-01 8482E-01 6031E-01
8 6811E-01 9382E-01 1140E+00 1212E+00 1247E+00 1219E+00 1114E+00 9962E-01 8482E-01 6031E-01
9 6811E-01 9381E-01 1140E+00 1212E+00 1247E+00 1219E+00 1114E+00 9961E-01 8491E-01 6031E-01
10 7089E-01 9529E-01 1132E+00 1192E+00 1218E+00 1192E+00 1108E+00 1005E+00 8639E-01 6279E-01
11 7391E-01 9701E-01 1123E+00 1171E+00 1185E+00 1162E+00 1100E+00 1014E+00 8801E-01 6551E-01
12 7509E-01 9759E-01 1119E+00 1162E+00 1173E+00 1151E+00 1098E+00 1018E+00 8869E-01 6659E-01
13 7750E-01 9900E-01 1112E+00 1145E+00 1147E+00 1127E+00 1092E+00 1025E+00 9000E-01 6870E-01
14 7920E-01 9990E-01 1106E+00 1133E+00 1129E+00 1110E+00 1088E+00 1031E+00 9090E-01 7030E-01
15 7982E-01 1002E+00 1104E+00 1128E+00 1123E+00 1104E+00 1086E+00 1032E+00 9123E-01 7082E-01
16 7983E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9124E-01 7083E-01
JAEA-DataCode 2013-009
- 232 -
17 7983E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9124E-01 7083E-01
18 7983E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9124E-01 7083E-01
19 7983E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9124E-01 7083E-01
20 7983E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9124E-01 7083E-01
21 7983E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9124E-01 7083E-01
22 7983E-01 1002E+00 1104E+00 1128E+00 1122E+00 1104E+00 1086E+00 1032E+00 9124E-01 7083E-01
DTIME(DAY) = 2000 ZMAX(CM) = 10000 ISTP = 22 DINCR= 010
ISTP KDIS TIMX(DAY) PLHR(WCM)
1 1 085 001 10591
2 2 39961 10805 23591
3 3 49284 23746 25646
4 4 57941 25814 27726
5 5 63136 27834 25914
6 6 66795 25981 25019
7 7 68141 25035 9629
8 8 68151 9629 096
9 9 68237 096 9629
10 10 82750 9714 19427
11 11 94293 19615 21577
12 12 98803 21660 20675
13 13 108149 20833 20337
14 14 115513 20453 18956
15 15 118133 18992 17992
16 16 118186 17993 600
17 17 118736 600 16993
18 18 124290 16993 15994
19 19 133673 15994 14994
20 20 140360 14994 13994
21 21 151608 13994 10996
22 22 151608 10996 10996
ISTEP KDIS TIMX(DAY) PLHR(WCM) POWER(MW)
1 1 085 5295 000529
2 2 2078 11124 001112
3 2 4072 11763 001176
4 2 6066 12402 001240
5 2 8060 13041 001304
6 2 10054 13680 001368
7 2 12047 14320 001432
8 2 14041 14959 001496
9 2 16035 15598 001560
10 2 18029 16237 001624
11 2 20023 16877 001688
12 2 22016 17516 001752
13 2 24010 18155 001816
14 2 26004 18794 001879
15 2 27998 19434 001943
16 2 29992 20073 002007
17 2 31985 20712 002071
18 2 33979 21351 002135
19 2 35973 21991 002199
20 2 37967 22630 002263
21 2 39961 23269 002327
22 3 41825 23934 002393
23 3 43690 24314 002431
24 3 45555 24694 002469
25 3 47419 25073 002507
26 3 49284 25453 002545
27 4 51015 26003 002600
28 4 52747 26385 002638
JAEA-DataCode 2013-009
- 233 -
29 4 54478 26767 002677
30 4 56210 27150 002715
31 4 57941 27532 002753
32 5 59673 27514 002751
33 5 61404 26874 002687
34 5 63136 26234 002623
35 6 64965 25738 002574
36 6 66795 25257 002526
37 7 68141 17329 001733
38 8 68151 4862 000486
39 9 68237 4862 000486
40 10 70051 10322 001032
41 10 71865 11536 001154
42 10 73679 12751 001275
43 10 75494 13965 001396
44 10 77308 15179 001518
45 10 79122 16393 001639
46 10 80936 17608 001761
47 10 82750 18822 001882
48 11 84673 19777 001978
49 11 86597 20103 002010
50 11 88521 20430 002043
51 11 90445 20757 002076
52 11 92369 21084 002108
53 11 94293 21411 002141
54 12 95796 21498 002150
55 12 97299 21170 002117
56 12 98803 20841 002084
57 13 100672 20783 002078
58 13 102541 20684 002068
59 13 104410 20585 002059
60 13 106279 20486 002049
61 13 108149 20387 002039
62 14 109990 20266 002027
63 14 111831 19892 001989
64 14 113672 19517 001952
65 14 115513 19143 001914
66 15 116823 18736 001874
67 15 118133 18237 001824
68 16 118186 9293 000929
69 17 118736 8793 000879
70 18 120588 16820 001682
71 18 122439 16487 001649
72 18 124290 16154 001615
73 19 126166 15888 001589
74 19 128043 15688 001569
75 19 129920 15488 001549
76 19 131797 15288 001529
77 19 133673 15088 001509
78 20 135345 14863 001486
79 20 137017 14613 001461
80 20 138689 14363 001436
81 20 140360 14113 001411
82 21 142235 13739 001374
83 21 144110 13239 001324
84 21 145984 12740 001274
85 21 147859 12240 001224
86 21 149733 11741 001174
87 21 151608 11241 001124
88 22 151608 10992 001099
89 22 153503 18560 001856
90 22 155398 18560 001856
91 22 157293 18560 001856
92 22 159189 18560 001856
93 22 161084 18560 001856
94 22 162979 18560 001856
95 22 164874 18560 001856
96 22 166769 18560 001856
RODBURN SUB CODE RABBLE INPUT CONDITION amp CALCULATION RESULT
NO CELL REGIONS = 39 NO MATERIALS = 12
NO COMPOSITIONS = 39 NO RESONANT MATERIALS = 2
JAEA-DataCode 2013-009
- 234 -
NO BROAD GROUPS = 12 LETHARGY WIDTH INTER GROUP =0100000E-01
NO INTERMEDIATE GROUPS = 885 RESONANCETEST = 0500E-02 (BARNS)
CIRCULARIZED CELL WITH COSINE INTERFACE CURRENTS
REGION 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18
COMPOSITION 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18
OUTER DIMENSION 0068 0097 0118 0137 0153 0167 0181 0193 0205 0216 0227 0237 0246 0256 0265 0273 0282 0290
TEMPERATURE 1266 1252 1238 1225 1211 1197 1183 1169 1155 1141 1127 1113 1100 1086 1072 1058 1044 1030
REGION 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36
REGION 37 38 39
COMPOSITION 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36
COMPOSITION 37 38 39
OUTER DIMENSION 0298 0306 0313 0320 0328 0335 0342 0348 0355 0362 0368 0374 0380 0387 0393 0398 0404 0410
OUTER DIMENSION 0485 0694 0903
TEMPERATURE 1016 1002 988 975 961 947 933 919 905 891 877 863 850 836 822 808 794 780
TEMPERATURE 613 593 593
MATERIAL RES MASS SIG POT SIG A 1V SIG F 1V COMPOSITIONDENSITY
(AMU) (BARNS) (BARNS) (BARNS) 1 2 3 4 5
U238 190 238051E+02 118230E+01 000000E+00 000000E+00 222878E-02 222878E-02 222878E-02 222878E-02 222878E-02
222878E-02 222878E-02 222878E-02 222878E-02 222878E-02
222878E-02 222878E-02 222878E-02 222878E-02 222878E-02
222878E-02 222878E-02 222878E-02 222878E-02 222878E-02
222878E-02 222878E-02 222878E-02 222878E-02 222878E-02
222878E-02 222878E-02 222878E-02 222878E-02 222878E-02
222878E-02 222878E-02 222878E-02 222878E-02 222878E-02
222878E-02 000000E+00 000000E+00 000000E+00
P240 200 240054E+02 109860E+01 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00
H 0 100783E+00 204280E+01 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 472045E-02 472045E-02
D 0 201431E+00 559400E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00
O 0 159949E+01 290700E+00 000000E+00 000000E+00 464810E-02 464810E-02 464810E-02 464810E-02 464810E-02
464810E-02 464810E-02 464810E-02 464810E-02 464810E-02
464810E-02 464810E-02 464810E-02 464810E-02 464810E-02
464810E-02 464810E-02 464810E-02 464810E-02 464810E-02
464810E-02 464810E-02 464810E-02 464810E-02 464810E-02
464810E-02 464810E-02 464810E-02 464810E-02 464810E-02
464810E-02 464810E-02 464810E-02 464810E-02 464810E-02
464810E-02 000000E+00 237570E-02 237570E-02
HE 0 400259E+00 136800E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00
ZR-2 0 913870E+01 647900E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
JAEA-DataCode 2013-009
- 235 -
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00
ZR-4 0 913950E+01 647900E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 431582E-02 000000E+00 000000E+00
U235 0 235044E+02 115000E+01 000000E+00 000000E+00 940538E-04 940538E-04 940538E-04 940538E-04 940538E-04
940538E-04 940538E-04 940538E-04 940538E-04 940538E-04
940538E-04 940538E-04 940538E-04 940538E-04 940538E-04
940538E-04 940538E-04 940538E-04 940538E-04 940538E-04
940538E-04 940538E-04 940538E-04 940538E-04 940538E-04
940538E-04 940538E-04 940538E-04 940538E-04 940538E-04
940538E-04 940538E-04 940538E-04 940538E-04 940538E-04
940538E-04 000000E+00 000000E+00 000000E+00
P239 0 239053E+02 112930E+01 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00
P241 0 241057E+02 125660E+01 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00
P242 0 242059E+02 123160E+01 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00 000000E+00
000000E+00 000000E+00 000000E+00 000000E+00
BROAD GROUP NO INTER GROUPS NO FINE GPINTER GP MAXIMUN ENERGY (EV) MINIMUM ENERGY (EV)
1 45 20 03519E+04 02244E+04
2 45 20 02244E+04 01431E+04
3 45 20 01431E+04 09123E+03
4 91 20 09123E+03 03672E+03
5 90 20 03672E+03 01493E+03
6 68 20 01493E+03 07564E+02
7 45 20 07564E+02 04823E+02
8 55 20 04823E+02 02783E+02
9 55 20 02783E+02 01605E+02
10 48 20 01605E+02 09934E+01
11 90 20 09934E+01 04039E+01
12 208 20 04039E+01 05046E+00
ABSORPTION 1 GROUPS
U238 11032E+00 11164E+00 11273E+00 11378E+00 11482E+00 11585E+00 11692E+00 11803E+00 11916E+00 12031E+00
12152E+00 12279E+00 12414E+00 12563E+00 12720E+00 12888E+00 13066E+00 13259E+00 13469E+00 13700E+00
13951E+00 14229E+00 14544E+00 14901E+00 15314E+00 15785E+00 16351E+00 17048E+00 17931E+00 19097E+00
20711E+00 23069E+00 26701E+00 32670E+00 43343E+00 63435E+00 00000E+00 00000E+00 00000E+00
P240 54437E+02 54422E+02 54412E+02 54398E+02 54386E+02 54375E+02 54364E+02 54354E+02 54344E+02 54333E+02
54323E+02 54312E+02 54301E+02 54292E+02 54282E+02 54273E+02 54263E+02 54252E+02 54241E+02 54230E+02
54219E+02 54207E+02 54194E+02 54181E+02 54168E+02 54152E+02 54136E+02 54118E+02 54098E+02 54077E+02
54054E+02 54027E+02 53994E+02 53955E+02 53902E+02 53823E+02 00000E+00 00000E+00 00000E+00
FISSION 1 GROUPS
U238 89217E-05 89168E-05 89130E-05 89097E-05 89066E-05 89037E-05 89009E-05 88980E-05 88953E-05 88927E-05
JAEA-DataCode 2013-009
- 236 -
88900E-05 88874E-05 88846E-05 88816E-05 88787E-05 88757E-05 88728E-05 88699E-05 88669E-05 88639E-05
88608E-05 88577E-05 88546E-05 88513E-05 88480E-05 88447E-05 88411E-05 88373E-05 88333E-05 88289E-05
88241E-05 88186E-05 88122E-05 88045E-05 87943E-05 87797E-05 00000E+00 00000E+00 00000E+00
P240 23082E-01 23089E-01 23094E-01 23098E-01 23103E-01 23107E-01 23112E-01 23116E-01 23121E-01 23125E-01
23129E-01 23134E-01 23139E-01 23144E-01 23149E-01 23155E-01 23161E-01 23166E-01 23172E-01 23179E-01
23185E-01 23192E-01 23200E-01 23207E-01 23216E-01 23224E-01 23233E-01 23243E-01 23254E-01 23266E-01
23279E-01 23295E-01 23312E-01 23331E-01 23353E-01 23376E-01 00000E+00 00000E+00 00000E+00
ABSORPTION RESONANCE INTEGRAL
U238 14935E+01 15122E+01 15276E+01 15424E+01 15570E+01 15715E+01 15865E+01 16021E+01 16180E+01 16340E+01
16509E+01 16687E+01 16877E+01 17084E+01 17304E+01 17538E+01 17786E+01 18054E+01 18347E+01 18667E+01
19016E+01 19402E+01 19839E+01 20333E+01 20905E+01 21555E+01 22338E+01 23300E+01 24517E+01 26125E+01
28349E+01 31596E+01 36597E+01 44817E+01 59527E+01 87265E+01 00000E+00 00000E+00 00000E+00
P240 72101E+03 72125E+03 72145E+03 72155E+03 72166E+03 72176E+03 72187E+03 72199E+03 72209E+03 72217E+03
72226E+03 72235E+03 72245E+03 72259E+03 72272E+03 72286E+03 72298E+03 72310E+03 72321E+03 72333E+03
72344E+03 72355E+03 72366E+03 72377E+03 72388E+03 72395E+03 72404E+03 72412E+03 72420E+03 72429E+03
72439E+03 72449E+03 72460E+03 72473E+03 72489E+03 72506E+03 00000E+00 00000E+00 00000E+00
FISSION RESONANCE INTEGRAL
U238 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03
12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03
12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03
12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 12078E-03 00000E+00 00000E+00 00000E+00
P240 30572E+00 30600E+00 30620E+00 30639E+00 30656E+00 30672E+00 30689E+00 30705E+00 30721E+00 30737E+00
30752E+00 30768E+00 30785E+00 30803E+00 30821E+00 30840E+00 30858E+00 30877E+00 30896E+00 30916E+00
30936E+00 30957E+00 30979E+00 31001E+00 31025E+00 31048E+00 31073E+00 31100E+00 31129E+00 31161E+00
31197E+00 31238E+00 31284E+00 31339E+00 31406E+00 31490E+00 00000E+00 00000E+00 00000E+00
TIME STEP NO 44 TIME = 77308 DAYS FLUX = 29345E+13 NCM2SEC
RADAIL DISTRIBUTION AXIAL SEGMENT NO 1 AXIAL COODINATE(CM) = 500
RADIAL COODI POWER POWER BURNUP BURNUP BURNUP THERM FLUX FAST FLUX FAST FLUEN
NO (CM) (MW) (WCM3) (MWD) (MWDT-U) (MWDTUO2) (NCM2S) (NCM2S) (NCM2)
1 0048 26083E-05 17781E+02 26057E-02 19355E+04 17060E+04 17231E+13 23886E+13 17778E+21
2 0084 26154E-05 17829E+02 26095E-02 19383E+04 17084E+04 17230E+13 23884E+13 17777E+21
3 0108 26223E-05 17876E+02 26143E-02 19419E+04 17116E+04 17241E+13 23899E+13 17791E+21
4 0128 26294E-05 17924E+02 26198E-02 19460E+04 17152E+04 17256E+13 23920E+13 17810E+21
5 0145 26368E-05 17975E+02 26257E-02 19504E+04 17191E+04 17274E+13 23945E+13 17833E+21
6 0160 26445E-05 18027E+02 26321E-02 19551E+04 17232E+04 17295E+13 23975E+13 17859E+21
7 0174 26526E-05 18082E+02 26389E-02 19601E+04 17277E+04 17319E+13 24007E+13 17888E+21
8 0187 26612E-05 18141E+02 26462E-02 19656E+04 17325E+04 17344E+13 24043E+13 17921E+21
9 0199 26700E-05 18201E+02 26539E-02 19713E+04 17376E+04 17372E+13 24081E+13 17955E+21
10 0211 26791E-05 18263E+02 26619E-02 19772E+04 17428E+04 17400E+13 24120E+13 17991E+21
11 0221 26885E-05 18327E+02 26702E-02 19834E+04 17482E+04 17430E+13 24161E+13 18028E+21
12 0232 26985E-05 18395E+02 26789E-02 19898E+04 17539E+04 17460E+13 24203E+13 18067E+21
13 0242 27090E-05 18467E+02 26880E-02 19966E+04 17599E+04 17491E+13 24246E+13 18106E+21
14 0251 27205E-05 18545E+02 26977E-02 20038E+04 17662E+04 17524E+13 24292E+13 18148E+21
15 0260 27326E-05 18628E+02 27079E-02 20114E+04 17729E+04 17558E+13 24340E+13 18191E+21
16 0269 27455E-05 18716E+02 27187E-02 20194E+04 17800E+04 17594E+13 24388E+13 18235E+21
17 0278 27589E-05 18807E+02 27299E-02 20277E+04 17873E+04 17629E+13 24437E+13 18280E+21
18 0286 27733E-05 18905E+02 27418E-02 20366E+04 17951E+04 17665E+13 24488E+13 18328E+21
19 0294 27889E-05 19011E+02 27547E-02 20461E+04 18035E+04 17704E+13 24541E+13 18377E+21
20 0302 28059E-05 19127E+02 27685E-02 20564E+04 18126E+04 17745E+13 24598E+13 18430E+21
21 0309 28246E-05 19255E+02 27834E-02 20675E+04 18224E+04 17789E+13 24659E+13 18486E+21
22 0317 28452E-05 19396E+02 27998E-02 20796E+04 18331E+04 17836E+13 24725E+13 18545E+21
23 0324 28682E-05 19552E+02 28176E-02 20929E+04 18447E+04 17886E+13 24793E+13 18607E+21
24 0331 28936E-05 19725E+02 28368E-02 21071E+04 18573E+04 17934E+13 24861E+13 18669E+21
25 0338 29223E-05 19921E+02 28581E-02 21230E+04 18712E+04 17984E+13 24929E+13 18733E+21
26 0345 29545E-05 20141E+02 28817E-02 21405E+04 18867E+04 18035E+13 25000E+13 18799E+21
27 0352 29926E-05 20400E+02 29086E-02 21605E+04 19043E+04 18087E+13 25073E+13 18868E+21
28 0358 30386E-05 20714E+02 29402E-02 21839E+04 19250E+04 18142E+13 25149E+13 18938E+21
29 0365 30968E-05 21110E+02 29793E-02 22130E+04 19506E+04 18207E+13 25239E+13 19020E+21
30 0371 31728E-05 21628E+02 30290E-02 22499E+04 19831E+04 18280E+13 25339E+13 19110E+21
31 0377 32759E-05 22331E+02 30944E-02 22985E+04 20259E+04 18357E+13 25447E+13 19206E+21
32 0384 34240E-05 23341E+02 31858E-02 23664E+04 20858E+04 18441E+13 25564E+13 19312E+21
33 0390 36491E-05 24875E+02 33218E-02 24674E+04 21748E+04 18534E+13 25692E+13 19430E+21
34 0396 40146E-05 27367E+02 35378E-02 26278E+04 23162E+04 18633E+13 25830E+13 19558E+21
35 0401 46609E-05 31773E+02 39137E-02 29070E+04 25623E+04 18739E+13 25975E+13 19693E+21
36 0407 58652E-05 39982E+02 46091E-02 34236E+04 30176E+04 18849E+13 26129E+13 19836E+21
RADAIL DISTRIBUTION AXIAL SEGMENT NO 2 AXIAL COODINATE(CM) = 1500
RADIAL COODI POWER POWER BURNUP BURNUP BURNUP THERM FLUX FAST FLUX FAST FLUEN
NO (CM) (MW) (WCM3) (MWD) (MWDT-U) (MWDTUO2) (NCM2S) (NCM2S) (NCM2)