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Page 1: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions
Page 2: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.2 of 63

Rev.0

TABLE OF CONTENTS

Section Page

LIST OF TABLES...............................................................................................................................................................3

LIST OF FIGURES.............................................................................................................................................................3

LIST OF APPENDICES .....................................................................................................................................................3

1.0 INTRODUCTION......................................................................................................................................................4

2.0 OPEN ITEMS ...........................................................................................................................................................4

3.0 REFERENCES.........................................................................................................................................................5

4.0 INPUTS AND ASSUMPTIONS ................................................................................................................................7

5.0 ANALYTICAL METHODS AND COMPUTATIONS.................................................................................................10

6.0 RESULTS................................................................................................................................................................14

7.0 CONCLUSION.........................................................................................................................................................15

8.0 ATTACHMENTS AND APPENDICES.....................................................................................................................15

Page 3: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.3 of 63

Rev.0

List of TablesTable 1 – SDU Design Features and Differences............................................................................................................ 4Table 2 – Radiation Zoning Criteria.................................................................................................................................. 4Table 3 – Source Terms ................................................................................................................................................... 7Table 4 – Material Compositions, Weight Fractions & Densities ..................................................................................... 8Table 5 – ICRP 74 Gamma Flux-to-Dose Rate Conversion Factors ............................................................................... 8Table 6 – SDU6 Rooftop Penetration Dimensions ........................................................................................................... 9Table 7 – Victaulic

®Cap Dimensions............................................................................................................................... 9

Table 8 – SDU6 Transfer Line Dimensions...................................................................................................................... 9Table 9 – Source Energy Grouping and Distribution by Source Term........................................................................... 10Table 10 – ORIGEN-ARP Input and Output Files ............................................................................................................ 11Table 11 – Detector Tally Multipliers................................................................................................................................ 14

List of FiguresFigure 1 – SDU 6 Schematic Model...................................................................................................................................7

List of Appendices

Appendix A – SDU 6 Dose Rate Profile MCNP Models’ Details .................................................................................. 16Appendix B – SDU 6 Rooftop Penetration MCNP Models’ Details .............................................................................. 19Appendix C – SDU 6 Transfer Line MCNP Models’ Details ......................................................................................... 23Appendix D – Example ORIGEN-ARP Input File (015L.inp) for 0.15 Ci/gal DSS ........................................................ 24Appendix E – Example ORIGEN-ARP Input File (015G.inp) for Grout Made from 0.15 Ci/gal DSS........................... 25Appendix F – List of MCNP Input and Output Files ..................................................................................................... 26Appendix G – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile ....................................................... 30Appendix H – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration .................................................. 43Appendix I – Example MCNP Input File (GL015) for SDU 6 Transfer Line ................................................................ 52Appendix J – SDU 6 Dose Rate Profile (mrem/hr) for 0.0002 Ci/gal Grout................................................................. 55Appendix K – SDU 6 Dose Rate Profile (mrem/hr) for 0.006 Ci/gal Grout................................................................... 56Appendix L – SDU 6 Dose Rate Profile (mrem/hr) for 0.015 Ci/gal Grout................................................................... 57Appendix M – SDU 6 Dose Rate Profile (mrem/hr) for 0.03 Ci/gal Grout..................................................................... 58Appendix N – Dose Rates Through SDU 6 Rooftop Penetrations ............................................................................... 59Appendix O – Dose Rates from SDU 6 Transfer Lines ................................................................................................ 60Appendix P – Estimated Dose Rates to Equipment Submersed in the SDU 6 Drainwell ............................................ 62Appendix Q – Total Absorbed Dose Estimate to SDU 6 Liner ..................................................................................... 63

Page 4: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.4 of 63

Rev.0

1.0 INTRODUCTION

In order to meet additional SDU capacity requirements, SDU 6 will be a different design than previous SDUs [Ref. 3.1]. Rather than a 2- or 4-pack configuration of smaller cylindrical tanks (i.e., SDUs 2, 3 and 5), SDU 6 will be a much larger, single tank design containing grout made from decontaminated salt solution (DSS) [Refs. 3.2, 3.3 & 3.4]. The major design differences between SDUs 2, 3 and 5 and SDU 6 affecting radiation dose rates and shielding are highlighted below in Table 1.

Table 1 – SDU Design Features and Differences

Design Feature SDUs 2, 3 & 5 SDU 6

Nominal Capacity 2.6 million gallons/tank ~32 million gallons/tank

DimensionsInner Diameter = 150’

Inner Height = 22’Inner Diameter = 375’ (average)

Inner Height = 43’Wall Thickness Uniform: 8” @ Top & Bottom Tapering: 10” @ Top; 24” @ BottomRoof Thickness Uniform: 8” Uniform: 12”

Because of these design differences a calculation is necessary to estimate dose rates on and around the new SDU 6 (i.e., a dose rate profile) and evaluate the effectiveness of its bulk shielding (i.e., wall and roof thicknesses). Additionally, dose rates through open and covered rooftop penetrations and from unshielded transfer lines (i.e., grout and leachate) will be evaluated. The Radiological Engineering & Health Physics (RE&HP) group routinely uses the Monte Carlo N-Particle (MCNP) radiation transport computer code to accomplish this [Ref. 3.5]. The radiological objective of these evaluations is to incorporate appropriate shielding into the SDU 6 design to maintain general area tank top and rooftop penetration dose rates as Radiation Zone 4 or lower (i.e., RBA, RA) and avoid Radiation Zones 5 and 6 (i.e., HRA, VHRA). Calculation results can also be compared to radiation zoning criteria to assist facility RadCon in developing appropriate radiological postings and access controls once SDU 6 becomes operational [Ref. 3.6; see Table 2 below].

Table 2 – Radiation Zoning Criteria

RadiationZone

Design Basis Maximum Area Radiation Dose Rate(mrem/hr)

Description

1 D<0.05 (@ 30 cm) Non-Rad Continuous Occupancy2 D>0.05 and D<0.5 (@ 30 cm) Rad-Worker Continuous Occupancy RBA

1

3 D>0.5 and D<5.0 (@ 30 cm) Intermittent Occupancy RBA1

4 D>5.0 and D<100 (@ 30 cm) Radiation Area (RA)5 D>100 @ 30 cm and D<500,000 mrad/hr @ 100 cm High Radiation Area (HRA)6 D>500,000 mrad/hr @ 100 cm Very High Radiation Area (VHRA)

1Radiological Buffer Area (RBA)

As a late addition to this calculation, the SDU 6 Design Authority (DA) also requested RE&HP to perform a dose rate estimate to equipment submersed in the SDU 6 drainwell and an estimate of the 10,000-year integrated absorbed dose to the high density polyethylene (HDPE) SDU6 liner. The DA requested these estimates to be based on two previously performed calculations rather than via new calculations. These estimates are incorporated in this calculation in Appendices P and Q, respectively.

2.0 OPEN ITEMS

None

Page 5: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.5 of 63

Rev.0

3.0 REFERENCES

3.1 SRR-LWP-2009-00001, Rev. 18, Liquid Waste System Plan, 6/24/13.3.2 G-ESR-Z-00011, Rev. 2, Saltstone Disposal Unit 6 Engineering Execution Plan, 11/8/12.3.3 M-TC-Z-00008, Rev. 5, Task Requirements and Criteria Document – Saltstone Facility Disposal Unit #6 Project,

Bldg. 451-006Z (U), 11/7/12.3.4 SRS Drawing Package for Z Area Saltstone Disposal Site SDU 6 Tank Design, Rev. 0, 11/9/12:

a. C-C2-Z-00002, Cover Sheet;b. C-C2-Z-00004, Abbreviations;c. C-C2-Z-00005, General Structural Notes;d. C-C2-Z-00007, Statement of Special Inspections;e. C-C2-Z-00008, Statement of Special Inspections;f. C-C2-Z-00009, Statement of Special Inspections;g. C-CY-Z-00005, HDPE/GCL, Leakage Detection and Settlement Monitoring Plan;h. C-CY-Z-00006, Leakage Detection System Sections and Details;i. C-CY-Z-00007, Leakage Detection and Settlement Monitoring Sections and Details;j. C-CC-Z-00039, Foundation Plan;k. C-CC-Z-00040, Overall Roof Plan;l. C-CC-Z-00049, Roof Embed and Nozzle Plan (Page 1 of 5);m. C-CC-Z-00049, Roof Embed and Nozzle Plan (Page 2 of 5);n. C-CC-Z-00049, Roof Embed and Nozzle Plan (Page 3 of 5);o. C-CC-Z-00049, Roof Embed and Nozzle Plan (Page 4 of 5);p. C-CC-Z-00049, Roof Embed and Nozzle Plan (Page 5 of 5);q. C-CC-Z-00041, Partial Roof Plan;r. C-CC-Z-00042, Wall and Column Section and Details;s. C-CC-Z-00043, Typical Roof Sections;t. C-CC-Z-00044, Concrete Sections and Details;u. C-CC-Z-00045, Concrete Details;v. C-CM-Z-00013, Ladder, Stair and Handrail Details;w. C-CM-Z-00019, Miscellaneous Steel Details;x. C-CC-Z-00046, Concrete Details;y. C-CM-Z-00014, Stair Tower Plan, Section and Elevations; andz. C-CM-Z-00020, Stair Tower Details.

3.5 Monte Carlo N-Particle Version 5 Transport Code, MCNP5_RSICC, 1.51, Los Alamos National Laboratory, 2008.3.6 SRS Engineering Standards Manual WSRC-TM-95-1, Standard No. 01064, Rev. 7, Radiological Design

Requirements, 1/24/12.3.7 U-ESR-Z-00012, Rev. 1, SDU 3/5 Project Engineering Execution Plan (EEP), 11/8/12.3.8 N-ESR-Z-00001, Rev. 1, Technical Justification for Shielding Design Basis Values Supporting Salt Disposition

Integration (SDI) Modifications at the Saltstone Production Facility (SDP), 6/27/12.3.9 X-ESR-H-00423, Rev. 0, Tank 50 Material Balance Update through August ’12, 10/4/12.3.10 X-ESR-H-00456, Rev. 0, Estimated Cesium Concentration in Tank 50, 1/17/13.3.11 PNNL-15870, Rev. 1, Compendium of Material Composition Data for Radiation Transport Modeling, March 2011.3.12 Savannah River Nuclear Solutions – Health Physics Services, Radiological Toolbox, Version 2.0.0, August 2006.3.13 S-CLC-Z-00041, Rev. 0, Salt Feed Line and Grout Line Shielding for Saltstone 0.2 Ci/gal Modifications, 5/9/05.3.14 U-TC-Z-00001, Rev. 8, Task Requirements and Criteria Document, Salt Solution Receipt Tanks - Saltstone Facility

Modifications, 11/16/12.3.15 ICRP 74, Conversion Coefficients for use in Radiological Protection against External Radiation, Pergamon Press,

1996.3.16 Victaulic

®Carbon Steel Pipe – Grooved Fittings 07.01, Rev. R, 08/12.

<http://static.victaulic.com/assets/uploads/literature/07.01.pdf>3.17 N-CSE-Z-00001, Rev. 0, Code/Standard Evaluation (CSE) – Saltstone Facility Grout Transfer Line Secondary

Containment & Leak Detection, 4/5/2013.3.18 ASTM A312/A312M, Standard Specification for Seamless, Welded, and Heavily Cold Worked Austenitic Stainless

Steel Pipes, www.astm.org, 2012.3.19 M-M6-Z-000129, Rev. 0, Z Area Saltstone Disposal Site SDU 6 Balance of Plant Drainwater Return System and

Leak Detection Piping & Instrumentation Diagram, 7/1/13.

Page 6: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.6 of 63

Rev.0

3.20 M-M6-Z-00128, Rev. 0, Z Area Saltstone Disposal Site SDU6 Balance of Plant 3" Grout Fill Line, 6/27/13.3.21 T-ESR-S-00010, Rev. 8, Engineering Report Defense Waste Processing Facility Piping Specifications January

2007, 7/27/10.3.22 ORNL/TM-2005/39, Rev. 5.1.01, ORIGEN-ARP: Automatic Rapid Processing for Spent Fuel Depletion, Decay, and

Source Term Analysis, March 2007.3.23 N-ISV-B-00007, Rev. 0, Initial Software Verification for Scale Version 6, 9/22/10.3.24 N-TR-B-00002, Rev. 0, Software Validation and Verification Report for MCNP5 and MCNP4C2, 7/10/06.3.25 N-CLC-Z-00022, Rev. 0, Dose Rates from Future Placement of Multiple Saltstone SDIP Disposal Cells Including

both 2- and 4-Pack Arrangements, 4/28/11.

Page 7: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.7 of 63

Rev.0

4.0 INPUTS AND ASSUMPTIONS

4.1 Source Terms

The predominant gamma (photon)-emitting radionuclide in the DSS and primary contributor to dose rates is Cesium-137 (Cs-137). This calculation considers eight (8) different source terms based on the following Cs-137concentrations (Ci/gal):

0.0002 Ci/gal DSS and its corresponding 0.000114 Ci/gal grout; 0.006 Ci/gal DSS and its corresponding 0.0034 Ci/gal grout; 0.015 Ci/gal DSS and its corresponding 0.00852 Ci/gal grout; and 0.03 Ci/gal DSS and its corresponding 0.017 Ci/gal grout.

[NOTE: Per Ref. 3.7, 1 gallon of DSS + dry materials = 1.76 gallons of grout.]

0.0002 Ci/gal DSS corresponds to design basis waste to be received from the Salt Waste Processing Facility [Ref. 3.8]. 0.006 Ci/gal (1.70E+06 pCi/ml) DSS corresponds to an intermediate level, non-design basis waste that has been received from the Actinide Removal Process and Modular Caustic Side Solvent Extraction Unit (ARP/MCU) through H-Tank Farm’s Tank 50 [Ref. 3.9]. 0.015 Ci/gal DSS corresponds to the revised design basis waste in SDUs 3 and 5 [Ref. 3.10]. 0.03 Ci/gal DSS corresponds to the original design basis waste in SDU 2 [Ref. 3.8]. The DSS source terms will be used in SDU 6 drainwater return line modeling. The grout source terms will be used in SDU6 dose rate profile, rooftop penetration and grout line modeling. All 8 source terms are comprised of five (5)gamma-emitting radionuclides at the concentrations presented in Table 3 below [Ref. 3.8].

Table 3 – Source Terms

0.0002 Ci/gal 0.006 Ci/gal 0.015 Ci/gal 0.03 Ci/galRadionuclide DSS Grout DSS Grout DSS Grout DSS Grout

Co-60 4.10E-06 2.33E-06 4.10E-06 2.33E-06 4.10E-06 2.33E-06 2.05E-05 1.16E-05Sb-125 3.36E-05 1.91E-05 3.36E-05 1.91E-05 3.36E-05 1.91E-05 1.68E-04 9.55E-05Cs-134 9.20E-07 5.23E-07 2.76E-05 1.57E-05 6.90E-05 3.92E-05 1.38E-04 7.84E-05Cs-137 2.00E-04 1.14E-04 6.00E-03 3.41E-03 1.50E-02 8.52E-03 3.00E-02 1.70E-02Eu-154 6.79E-06 3.86E-06 6.79E-06 3.86E-06 6.79E-06 3.86E-06 3.40E-05 1.93E-05

4.2 SDU 6 Dimensions [Ref. 3.4]

A simplified, cross-sectional schematic of the cylindrical SDU 6 model filled to 41’ with a 2’ vapor space is presented in Figure 1. It is in color for illustrative purposes, but not to scale. Exact dimensions modeled (in cm) are detailed in Appendix A. MCNP modeling conventions are detailed in Section 5.2.1. [NOTE: There are 208 concrete support columns inside SDU 6 that, for clarity, are not shown in Figure 1, but will be included in Appendix A.]

Figure 1 – SDU 6 Schematic Model(NOTE: Not to Scale)

Page 8: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

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4.3 Material Compositions, Weight Fractions and Densities

Material compositions, weight fractions and densities used in the MCNP models were taken from References 3.11, 3.12 and/or 3.13 and are presented in Table 4 below. The density of the DSS source term is assumed to be that of water at 0.998207 g/cc. This simplifies all MCNP models and is conservative because the actual density of DSS ranges from 1.20 - 1.25 g/cc [Ref. 3.14].

Table 4 – Material Compositions, Weight Fractions & Densities

ElementMaterial (Weight Fraction)

Grout Water Carbon Steel Stainless Steel(SS304L)

Dry Air Concrete

H-1 0.053479 0.111894 0.010000

C-6 0.005000 0.000150 0.000124 0.001000

N-7 0.755268

O-8 0.609656 0.888106 0.231781 0.529107

Na-11 0.016000

Mg-12 0.008697 0.002000

Al-13 0.046681 0.033872

Si-14 0.035886 0.005000 0.337021

P-15 0.000230

S-16 0.005398 0.000150

Ar-18 0.012827

K-19 0.013000

Ca-20 0.001100 0.044000

Ti-22 0.140544

Cr-24 0.190000

Mn-25 0.010000

Fe-26 0.098561 0.995000 0.694480 0.014000

Ni-28 0.100000

Total 1.00 1.00 1.00 1.00 1.00 1.00

Density (g/cc) 1.7007 0.998207 7.82 8.00 0.001205 2.3

4.4 Flux-to-Dose Rate Conversion Factors

The MCNP radiation transport computer code uses energy-dependent flux-to-dose rate conversion factors from Reference 3.15 to convert photon (gamma) energy flux at various locations of interest (i.e., detectors) to dose rates. They are presented in Table 5 below.

Table 5 – ICRP 74 Gamma Flux-to-Dose Rate Conversion Factors

Energy(MeV)

ConversionFactor

(mrem·hr-1/cm-2·s-1)

Energy(MeV)

ConversionFactor

(mrem·hr-1/cm-2·s-1)

Energy(MeV)

ConversionFactor

(mrem·hr-1/cm-2·s-1)

1.00E-02 2.4624E-05 8.00E-02 2.1100E-04 6.00E-01 1.2535E-03

1.50E-02 3.0508E-04 1.00E-01 2.4253E-04 8.00E-01 1.5808E-03

2.00E-02 3.8053E-04 1.50E-01 3.4711E-04 1.00E+00 1.8779E-03

3.00E-02 2.9584E-04 2.00E-01 4.5977E-04 1.50E+00 2.5094E-03

4.00E-02 2.3494E-04 3.00E-01 6.8012E-04 3.00E+00 3.9770E-03

5.00E-02 2.0853E-04 4.00E-01 8.8452E-04 6.00E+00 6.3080E-03

6.00E-02 1.9889E-04 5.00E-01 1.0761E-03 1.00E+01 9.2791E-03

Page 9: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.9 of 63

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4.5 SDU 6 Rooftop Penetrations

Seven different types of SDU 6 rooftop penetrations are evaluated (see Table 6 below) [Ref. 3.4].

Table 6 – SDU6 Rooftop Penetration Dimensions

Penetration DimensionsPipe Wall Thickness (t)

[Ref. 3.16]

Grout/Inspection Port(3” Diameter)

Outside Radius = 4.45 cmSchedule 40t = 0.55 cm

Thermocouple Port(8” Diameter)

Outside Radius = 10.95 cmSchedule 40t = 0.82 cm

Camera Port(12” Diameter)

Outside Radius = 16.19 cmSchedule 40t = 0.95 cm

Passive Vent(12” Diameter)

Outside Radius = 16.19 cmSchedule 40t = 0.95 cm

Active Vent(14” Diameter)

Outside Radius = 17.78 cmSchedule 5t = 0.4 cm

Drainwater Return Port(36” Diameter)

Outside Radius = 46.36 cmt = ¼” = 0.64 cm

[Ref. 3.4]Access Hatch

(6’ x 8’)182.88 cm x 243.84 cm n/a

Three of these penetrations (grout/inspection port, thermocouple port, camera port) were originally designed with appropriately sized, carbon steel Victaulic

®caps (see Table 7 below) [Ref. 3.16]. Since then Victaulic

®couplings

have been evaluated and their use at SDU 6 will be eliminated to the maximum extent practicable [Ref. 3. 17]. Their continued input to this calculation only serves to specify a carbon steel shielding thickness to be evaluated.

Table 7 – Victaulic®

Cap Dimensions

Rooftop penetration details are included in Appendix B. MCNP modeling conventions are detailed in Section 5.2.2.

4.6 SDU6 Transfer Lines

Two types of transfer lines are evaluated: a full 2” diameter Schedule 40 stainless steel drainwater return line and a full 3” diameter carbon steel grout line with a ¼” wall (see Table 8 below) [Refs. 3.18, 3.19, 3.20, 3.21].

Table 8 – SDU6 Transfer Line Dimensions

Transfer LineOutside Radius Wall Thickness Inside Radius Length

(cm) (cm) (cm) (ft) (cm)

Drainwater Return Line(2” Diameter)

3.02 0.39 2.63 100 3048

Grout Line(3” Diameter)

4.45 0.64 3.81 100 3048

Transfer line details are included in Appendix C. MCNP modeling conventions are detailed in Section 5.2.3.

Page 10: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

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Calculation Continuation Sheet

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5.0 ANALYTICAL METHODS AND COMPUTATIONS

5.1 Source Term Generation with ORIGEN-ARP Software [Ref. 3.22]

The radionuclide concentrations (Ci/gal) from each of the source terms in Table 3 were input into ORIGEN-ARP to generate source definition input for MCNP models. Normalized 18-group energy spectra for each source term showing each group’s corresponding total source strength (/sec/gal) and percent contribution to total are presented below in Table 9. The source strengths for the 0.0002 Ci/gal source terms, both DSS and grout, were maximized at a decay time of 0.1 years. The source strengths for the 0.006 Ci/gal, 0.015 Ci/gal and 0.03 Ci/gal source terms, both DSS and grout, were maximized at a decay time of 0.001 years.

Table 9 – Source Energy Grouping and Distribution by Source Term

Group

EnergyRange(MeV)

Source Terms

0.0002 Ci/gal DSS 0.0002 Ci/gal Grout 0.006 Ci/gal DSS 0.006 Ci/gal Grout

Strength/sec/gal)

%Contribution

Strength/sec/gal)

%Contribution

Strength/sec/gal)

%Contribution

Strength/sec/gal)

%Contribution

Min Max

1 0.01 0.05 1.390E+06 1.5258E-01 7.912E+05 1.5248E-01 1.849E+07 9.1762E-02 1.051E+07 9.1790E-02

2 0.05 0.10 1.155E+04 1.2678E-03 6.581E+03 1.2683E-03 2.834E+05 1.4065E-03 1.611E+05 1.4070E-03

3 0.10 0.20 1.910E+05 2.0966E-02 1.086E+05 2.0929E-02 3.192E+05 1.5841E-03 1.814E+05 1.5843E-03

4 0.20 0.30 2.464E+04 2.7047E-03 1.401E+04 2.6999E-03 4.978E+04 2.4705E-04 2.829E+04 2.4707E-04

5 0.30 0.40 2.583E+04 2.8353E-03 1.469E+04 2.8310E-03 3.619E+04 1.7960E-04 2.057E+04 1.7965E-04

6 0.40 0.60 6.061E+05 6.6531E-02 3.446E+05 6.6410E-02 1.487E+06 7.3797E-03 8.457E+05 7.3860E-03

7 0.60 0.80 6.327E+06 6.9451E-01 3.606E+06 6.9493E-01 1.798E+08 8.9231E-01 1.022E+08 8.9258E-01

8 0.80 1.00 8.721E+04 9.5730E-03 4.958E+04 9.5548E-03 4.993E+05 2.4779E-03 2.840E+05 2.4803E-03

9 1.00 1.33 3.691E+05 4.0516E-02 2.098E+05 4.0432E-02 3.999E+05 1.9846E-03 2.273E+05 1.9852E-03

10 1.33 1.66 7.714E+04 8.4676E-03 4.384E+04 8.4486E-03 1.055E+05 5.2357E-04 5.997E+04 5.2376E-04

11 1.66 2.00 1.111E+01 1.2195E-06 6.318E+00 1.2176E-06 1.120E+01 5.5583E-08 6.368E+00 5.5616E-08

12 2.00 2.50 1.596E+00 1.7519E-07 9.068E-01 1.7475E-07 1.617E+00 8.0248E-09 9.187E-01 8.0236E-09

13 2.50 3.00 1.363E-03 1.4962E-10 7.748E-04 1.4932E-10 1.381E-03 6.8536E-12 7.850E-04 6.8559E-12

14 3.00 4.00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

15 4.00 5.00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

16 5.00 6.50 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

17 6.50 8.00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

18 8.00 10.00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

Total 9.110E+06 1.000E+00 5.189E+06 1.000E+00 2.015E+08 1.000E+00 1.145E+08 1.000E+00

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Table 9 (continued) – Source Energy Grouping and Distribution by Source Term

Group

EnergyRange(MeV)

Source Terms

0.015 Ci/gal DSS 0.015 Ci/gal Grout 0.03 Ci/gal DSS 0.03 Ci/gal Grout

Strength/sec/gal)

%Contribution

Strength/sec/gal)

%Contribution

Strength/sec/gal)

%Contribution

Strength/sec/gal)

%Contribution

Min Max

1 0.01 0.05 4.517E+07 9.0322E-02 2.566E+07 9.0320E-02 9.245E+07 9.1807E-02 5.239E+07 9.1767E-02

2 0.05 0.10 7.051E+05 1.4099E-03 4.005E+05 1.4097E-03 1.417E+06 1.4071E-03 8.029E+05 1.4064E-03

3 0.10 0.20 5.134E+05 1.0266E-03 2.917E+05 1.0268E-03 1.597E+06 1.5859E-03 9.061E+05 1.5871E-03

4 0.20 0.30 8.829E+04 1.7654E-04 5.016E+04 1.7656E-04 2.490E+05 2.4727E-04 1.413E+05 2.4750E-04

5 0.30 0.40 5.127E+04 1.0252E-04 2.913E+04 1.0253E-04 1.810E+05 1.7974E-04 1.028E+05 1.8007E-04

6 0.40 0.60 2.830E+06 5.6589E-03 1.608E+06 5.6600E-03 7.435E+06 7.3833E-03 4.225E+06 7.4006E-03

7 0.60 0.80 4.490E+08 8.9782E-01 2.550E+08 8.9757E-01 8.991E+08 8.9285E-01 5.095E+08 8.9245E-01

8 0.80 1.00 1.137E+06 2.2735E-03 6.460E+05 2.2738E-03 2.497E+06 2.4796E-03 1.418E+06 2.4838E-03

9 1.00 1.33 4.413E+05 8.8242E-04 2.508E+05 8.8279E-04 2.001E+06 1.9871E-03 1.134E+06 1.9863E-03

10 1.33 1.66 1.480E+05 2.9594E-04 8.410E+04 2.9602E-04 5.276E+05 5.2393E-04 2.989E+05 5.2356E-04

11 1.66 2.00 1.120E+01 2.2396E-08 6.368E+00 2.2415E-08 5.609E+01 5.5700E-08 3.184E+01 5.5772E-08

12 2.00 2.50 1.617E+00 3.2334E-09 9.187E-01 3.2337E-09 8.083E+00 8.0268E-09 4.574E+00 8.0119E-09

13 2.50 3.00 1.381E-03 2.7614E-12 7.850E-04 2.7631E-12 6.906E-03 6.8580E-12 3.908E-03 6.8453E-12

14 3.00 4.00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

15 4.00 5.00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

16 5.00 6.50 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

17 6.50 8.00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

18 8.00 10.00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.000E+00 0.0000E+00

Total 5.001E+08 1.000E+00 2.841E+08 1.000E+00 1.007E+09 1.000E+00 5.709E+08 1.000E+00

The ORIGEN-ARP code, a module of the well-established SCALE system of nuclear analysis codes, which wasused by RE&HP for this calculation, has been verified and validated [Ref. 3.23]. All ORIGEN-ARP modeling was performed on laptop computer V0043116 leased to RE&HP. All files associated with this calculation are stored and maintained in RE&HP’s workgroup folder ('wg07\wg07data\lwo rad engr'). A list of all ORIGEN-ARP input and output files are presented below in Table 10. Example ORIGEN-ARP input files for a DSS and grout source term are presented in Appendices D and E, respectively.

Table 10 – ORIGEN-ARP Input and Output Files

File Name File Type File Description

0002L.inp InputSource Term for 0.0002 Ci/gal DSS/Leachate

0002L.out Output0002G.inp Input

Source Term for Grout Made from 0.0002 Ci/gal DSS0002G.out Output006L.inp Input

Source Term for 0.006 Ci/gal DSS/Leachate006L.out Output006G.imp Input

Source Term for Grout Made from 0.006 Ci/gal DSS006G.out Output015L.inp Input

Source Term for 0.015 Ci/gal DSS/Leachate015L.out Output015G.imp Input

Source Term for Grout Made from 0.015 Ci/gal DSS015G.out Output03L.inp Input

Source Term for 0.03 Ci/gal DSS/Leachate03L.out Output03G.imp Input

Source Term for Grout Made from 0.03 Ci/gal DSS03G.out Output

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5.2 Radiation Transport Modeling with MCNP Software [Ref. 3.5]

Energy distribution spectra and their respective source strengths from Table 9 were input into the appropriate simplified, geometric MCNP models representing SDU 6, including penetrations in the roof, as well as transfer lines. The different conventions used in the various MCNP models are discussed in the following subsections.

The MCNP radiation transport code used by RE&HP for this calculation has been verified and validated [Ref. 3.24]. All MCNP modeling was performed on one of two laptop computers leased to RE&HP: V0043116 or V0044195. All files associated with this calculation are stored and maintained in RE&HP’s workgroup folder ('wg07\wg07data\lwo rad engr'). A list of MCNP input and output files is presented in Appendix F. Example input files for an SDU 6 dose rate profile, rooftop penetration and transfer lines are presented in Appendices G, H and I, respectively.

5.2.1 SDU 6 Dose Rate Profile MCNP Models

The following convention(s) were included in the SDU 6 dose rate profile MCNP models for ease of modeling,efficiency and/or conservatism:

The SDU outer concrete wall was modeled as a right circular cylinder, but the interior wall and cells were modeled as a series of layered or concentric, inverted truncated cones (geometrically referred to as frusta or frustums) to account for the interior taper from 10” thick at its top to 24” thick at its bottom.

The concrete roof and pad will be built with a 1.5% slope from its center to its perimeter, but are modeled asflat, right circular cylinders. Doing so is conservative as it maintains a constant distance, as opposed to a variable distance, between the contained grout source and any detectors above the rooftop. It has no effect on the grout source volume or strength.

The ~45’ tall SDU will be built in a terraced pit. For simplicity, however, it is modeled with no soil backfill at grade level. Volume detectors are strategically placed at numerous radial distances and elevations to account for any future backfill and/or sloped soil walls around the SDU.

Previous calculations involving grout-filled SDUs show that dose rates emanate primarily from the outer 50 cm of grout due to self-shielding [Ref. 3.25]. Therefore, only an outer 50-cm layer of grout is modeled for the source around an inner non-source (void) core.

208 concrete columns (@ 2’ diam.) are modeled only through the upper 50-cm grout source layer and the 2’ vapor space. No columns are modeled in the lower 50-cm source layer because no columns are that close to the wall (see Appendix A for column layout). Likewise, no columns are necessary to be modeled in the void core void. Column capitals and footings are not modeled. Likewise, no other interior equipment (e.g., sumps) are modeled. This is conservative as it maximizes the grout source volume.

The concrete slab and soil underneath are modeled as voids because downward gamma (photon) transport is negligible and of no interest to the dose rate profile. This will allow models to run more efficiently. Absorbed dose to the HDPE liner is estimated separately in Appendix Q.

The variable shotcrete coating and high density polyethylene (HDPE) liner outside the SDU wall are not modeled. This is conservative as they will not be credited as providing any shielding.

5.2.2 SDU 6 Rooftop Penetrations MCNP Models

Additional convention(s) were included in the SDU 6 rooftop penetrations MCNP models for ease of modeling, efficiency and/or conservatism:

All penetrations are modeled as right circular cylindrical openings in the SDU 6 rooftop except for the access hatch which is a rectangular (parallelepiped) opening. Likewise, respective caps and covers are modeled as cylinders and rectangles.

Only the upper 50 cm source is included due to grout self-shielding. The soil and slab are not included in this model. Everything underneath the source is modeled as void because

downward gamma (photon) transport is negligible and of no interest to the dose rate profile. This will allow models to run more efficiently.

The roof is modeled without any overhang at the same radius as the outer wall. This is done for simplicity and has no effect on penetration dose rates.

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Each penetration is individually modeled in the center of the rooftop rather than according to the roof penetration schedule in Ref. 3.4. This maximizes exposure to the grout source below, removes contribution from any other penetrations making it a more realistic representation, and simplifies each model.

Open and shielded configurations for each of the seven types of penetrations were evaluated (see Appendix B). Shielded configurations include both steel Victaulic

®Caps and steel flange covers of varying, nominal

thickness(es) to evaluate their shielding effectiveness.

5.2.3 Transfer Lines

Each transfer line was modeled as a 100’ long right circular cylinder. 100’ was chosen based on professional experience that longer lengths do not contribute appreciably to dose rates due to distance and self-shielding.

5.2.4 Variance Reduction Techniques

Geometry splitting with Russian roulette was included in the SDU 6 MCNP models used to determine dose rate profiles. In order to reduce MCNP run times and make the models run more efficiently, the thick roof and wall were split (segmented) into layers with thicknesses equal to 2-3 mean free path (MFP) lengths for Cs-137 gammas. Importances of increasing value were assigned to each layer as they moved away from the void core. Preliminary MCNP model runs indicated the 1 MFP for concrete was ~3.8 cm. Therefore, the 12” (30.48 cm) concrete roof was split into three 10.16 cm layers. The tapered concrete wall (10” or 25.4 cm at the top; 24” or 60.96 cm at thebottom) was split into 4 layers. This made the layers only 6.35 cm thick at the top and 15.24 cm at the bottom, but 10.8 cm in the middle.

Likewise, geometry splitting with Russian roulette was included in the SDU6 rooftop penetration models. Preliminary MCNP model runs indicated 1 MFP for grout was ~5.6 cm. Therefore, the 50-cm grout source was splitinto five 10 cm layers. Additionally, DXTRAN spheres were incorporated into several of the rooftop penetration models to increase the probability of particle interaction through the small penetration in relation to the large underlying grout source.

No advanced variance reduction techniques were necessary for the SDU 6 transfer line MCNP models.

5.2.5 Detector (“Tally”) Locations

For SDU 6 dose rate profile MCNP models, cylindrical volume detectors (“F4 tallies”) were placed 30 cm above the SDU as well as radially around the SDU at 4’, 10’, 20’, 30’ and 40’ elevations from the bottom of the SDU and at distances of 30 cm and in 10’ increments out to 380’ to provide dose rates on top of and around the SDU.

For SDU 6 rooftop penetration MCNP models, cylindrical volume detectors (“F4 tallies”) were place surrounding each penetration at a distance of 30 cm. Point detectors (“F5 tallies”) were also placed 30 cm above the grout pour in several of the rooftop penetration models to determine dose rates inside the SDU.

For SDU 6 transfer line MCNP models, ring detectors (“F5x tallies”) were placed around the midpoint (50’) of the lines at increasing radii, including 5 cm, 30 cm, and at 1’ increments from 2’ to 99’.

5.2.6 Detector (“Tally”) Multipliers

Because MCNP tallies report gamma flux on a volumetric basis, in addition to flux-to-dose rate conversion factors from Section 4.4 - Table 5, multipliers for each source term based on respective source volumes (from Appendices A, B and C) and source strengths (from Table 9) are necessary to convert the tallies to mrem/hr (see Table 11below).

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Table 11 – Detector Tally Multipliers

MCNP Model Source TermSource Strength

(/sec/gal)Source Volume

(gal)Tally Multiplier

(/sec)

SDU6 Dose Rate Profile

0.0002 Ci/gal Grout 5.189E+06 x

1,921,000

= 9.9681E+120.006 Ci/gal Grout 1.145E+08 x = 2.1995E+14

0.015 Ci/gal Grout 2.841E+08 x = 5.4576E+14

0.03 Ci/gal Grout 5.709E+08 x = 1.0967E+15

SDU6 Penetrations

0.0002 Ci/gal Grout 5.189E+06 x

1,354,631

= 7.0292E+12

0.006 Ci/gal Grout 1.145E+08 x = 1.5511E+14

0.015 Ci/gal Grout 2.841E+08 x = 3.8485E+14

0.03 Ci/gal Grout 5.709E+08 x = 7.7336E+14

SDU6 Drainwater Return Line

0.0002 Ci/gal DSS 9.110E+06 x

17.4925

= 1.5936E+08

0.006 Ci/gal DSS 2.015E_08 x = 3.5247E+09

0.015 Ci/gal DSS 5.001E+08 x = 8.7480E+09

0.03 Ci/gal DSS 1.007E+09 x = 1.7615E+10

SDU 6 Grout Line

0.0002 Ci/gal Grout 5.189E+06 x

38.4613

= 1.9958E+08

0.006 Ci/gal Grout 1.145E+08 x = 4.4038E+09

0.015 Ci/gal Grout 2.841E+08 x = 1.0927E+10

0.03 Ci/gal Grout 5.709E+08 x = 2.1958E+10

5.3 Data Manipulation with Microsoft Excel

Microsoft Excel was used to compile, manipulate and tabulate SDU 6 dimensions in the various appendices. It was also used in the same manner with the raw MCNP output files so they could be more easily presented as results.

6.0 RESULTS

Due to adequate computer run times and successful variance reduction techniques incorporated into all of the MCNP models, all results passed all ten built-in MCNP statistical checks. Models with point and ring detectors all produced results with associated relative errors < 5% and models with volume detectors all produced results withassociated relative errors < 10% both of which are below what MCNP considers reliable [Ref. 3.5]. Therefore, results in Appendices J, K, L, M, N and O are presented without associated errors. All relative errors are available in the corresponding MCNP output files maintained on RE&HP workgroup folder.

Dose rate profile results for SDU 6 containing grout made from 0.0002 Ci/gal DSS are presented in Appendix J.Dose rate profile results for SDU 6 containing grout made from 0.006 Ci/gal DSS are presented in Appendix K.Dose rate profile results for SDU 6 containing grout made from 0.015 Ci/gal DSS are presented in Appendix L.Dose rate profile results for SDU 6 containing grout made from 0.03 Ci/gal DSS are presented in Appendix M.Dose rates through SDU 6 rooftop penetrations are presented in Appendix N.Dose rates emanating from SDU 6 transfer lines are presented in Appendix O.Estimated dose rates to equipment submersed in the SDU 6 drainwell are presented in Appendix P.The estimated 10,000-year total absorbed dose to the SDU 6 Liner is presented in Appendix Q.

.

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7.0 CONCLUSION

For the 0.0002 Ci/gal, 0.006 Ci/gal and 0.015 Ci/gal source terms, the thickness of the SDU 6 concrete walls and roof will be adequate to maintain general area tank top dose rates < 5 mrem/hr @ 30 cm (i.e., Rad Zones 2 & 3 –Radiological Buffer Area). Only the 0.03 Ci/gal source term will result in general area tank top dose rates > 5 mrem/hr @ 30 cm, but < 100 mrem/hr @ 30 cm (i.e., Rad Zone 4 – Radiation Area). Dose rate profiles around SDU 6 will be vary greatly based on the Cs-137 content of the grout. The size of the RBA will range from the tanktop perimeter at 0.0002 Ci/gal out to 380’ from the perimeter for 0.03 Ci/gal.

In order to meet the radiological objective of Radiation Zone 4 or lower (i.e., RBA, RA), the following minimum amount of shielding (or equivalent) is recommended for the rooftop penetrations:

Access Hatch – 1’ concrete cover;Active Vent – ¼” steel cover/housingCamera Port – ½” steel coverDrainwater Return Port – ¼” steel cover;Grout/Inspection Port – ¼” steel cover;Passive Vent – ¼” steel cover/housing; andThermocouple Port – ½” steel cover.

Dose rates emanating from unshielded drainwater and grout lines also vary greatly based on their source term. Either full line could result in a RA out to 7’-8’ and an RBA out to >100’ depending on it Cs-137 content. If an RA is to be avoided, ¼”, ½” and ¾” of lead shielding (or equivalent) is required for both the drainwater or grout line at 0.006 Ci/gal, 0.015 Ci/gal and 0.03 Ci/gal, respectively. Neither the unshielded drainwater or grout line at 0.0002 Ci/gal ever results RA dose rates.

A wastewater pump submersed in 0.015 Ci/gal drainwater in the SDU6 drainwell is estimated to receive a total (alpha, beta and gamma; no neutron) dose rate of 6.0E+05 Rad/yr. The total 10,000-year absorbed dose to the SDU 6 liner is estimated to be ~17,000 Rad.

8.0 ATTACHMENTS AND APPENDICES

There are no Attachments.

Appendix A – SDU 6 Dose Rate Profile MCNP Models’ DetailsAppendix B – SDU 6 Rooftop Penetration MCNP Models’ DetailsAppendix C – SDU 6 Transfer Line MCNP Models’ DetailsAppendix D – Example ORIGEN-ARP Input File (015L.inp) for 0.15 Ci/gal DSSAppendix E – Example ORIGEN-ARP Input File (015G.inp) for Grout Made from 0.15 Ci/gal DSSAppendix F – List of MCNP Input and Output Files Appendix G – Example MCNP Input File (S6015N) for SDU 6 Dose Rate ProfileAppendix H – Example MCNP Input File (S63AHC) for SDU 6 Rooftop PenetrationAppendix I – Example MCNP Input File (GL015) for SDU 6 Transfer LineAppendix J – SDU 6 Dose Rate Profile (mrem/hr) for 0.0002 Ci/gal GroutAppendix K – SDU 6 Dose Rate Profile (mrem/hr) for 0.006 Ci/gal GroutAppendix L – SDU 6 Dose Rate Profile (mrem/hr) for 0.015 Ci/gal GroutAppendix M – SDU 6 Dose Rate Profile (mrem/hr) for 0.03 Ci/gal GroutAppendix N – Dose Rates Through SDU 6 Rooftop PenetrationsAppendix O – Dose Rates from SDU 6 Transfer LinesAppendix P – Estimated Dose Rates to Equipment Submersed in the SDU 6 DrainwellAppendix Q – Total Absorbed Dose Estimate to SDU 6 Liner

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Appendix A – SDU 6 Dose Rate Profile MCNP Models’ Details

SDU 6 Model [All Dimensions in centimeters (cm)](NOTE: Not to Scale; Columns not shown for clarity)

Typical Foundation Plan Showing 208 Columns (Ref. 3.4)(23’ x 23’ grid = 701.04 cm x 701.04 cm grid)

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Appendix A (continued) – Dimensions for Use in SDU 6 Dose Rate Profile MCNP Models

SDU 6 Interior Concrete Column Dimensions and Layout(x-coordinate, y-coordinate; cm)

x y x y x y

A x y x y -1752.6 5257.80 -1051.6 5257.80 -350.52 5257.80

B x y -3154.68 4556.76 -2453.64 4556.76 -1752.6 4556.76 -1051.6 4556.76 -350.52 4556.76

C x y -3855.72 3855.72 -3154.68 3855.72 -2453.64 3855.72 -1752.6 3855.72 -1051.6 3855.72 -350.52 3855.72

D -4556.76 3154.68 -3855.72 3154.68 -3154.68 3154.68 -2453.64 3154.68 -1752.6 3154.68 -1051.6 3154.68 -350.52 3154.68

E x y -4556.76 2453.64 -3855.72 2453.64 -3154.68 2453.64 -2453.64 2453.64 -1752.6 2453.64 -1051.6 2453.64 -350.52 2453.64

F -5257.8 1752.60 -4556.76 1752.60 -3855.72 1752.60 -3154.68 1752.60 -2453.64 1752.60 -1752.6 1752.60 -1051.6 1752.60 -350.52 1752.60

G -5257.8 1051.56 -4556.76 1051.56 -3855.72 1051.56 -3154.68 1051.56 -2453.64 1051.56 -1752.6 1051.56 -1051.6 1051.56 -350.52 1051.56

H -5257.8 350.52 -4556.76 350.52 -3855.72 350.52 -3154.68 350.52 -2453.64 350.52 -1752.6 350.52 -1051.6 350.52 -350.52 350.52

NW QUADRANT

321 87654

J -5257.8 -350.52 -4556.76 -350.52 -3855.72 -350.52 -3154.68 -350.52 -2453.64 -350.52 -1752.6 -350.52 -1051.6 -350.52 -350.52 -350.52

K -5257.8 -1051.56 -4556.76 -1051.56 -3855.72 -1051.56 -3154.68 -1051.56 -2453.64 -1051.56 -1752.6 -1051.56 -1051.6 -1051.56 -350.52 -1051.56

L -5257.8 -1752.60 -4556.76 -1752.60 -3855.72 -1752.60 -3154.68 -1752.60 -2453.64 -1752.60 -1752.6 -1752.60 -1051.6 -1752.60 -350.52 -1752.60

M x y -4556.76 -2453.64 -3855.72 -2453.64 -3154.68 -2453.64 -2453.64 -2453.64 -1752.6 -2453.64 -1051.6 -2453.64 -350.52 -2453.64

N -4556.76 -3154.68 -3855.72 -3154.68 -3154.68 -3154.68 -2453.64 -3154.68 -1752.6 -3154.68 -1051.6 -3154.68 -350.52 -3154.68

P x y -3855.72 -3855.72 -3154.68 -3855.72 -2453.64 -3855.72 -1752.6 -3855.72 -1051.6 -3855.72 -350.52 -3855.72

R x y -3154.68 -4556.76 -2453.64 -4556.76 -1752.6 -4556.76 -1051.6 -4556.76 -350.52 -4556.76

S x y x y -1752.6 -5257.80 -1051.6 -5257.80 -350.52 -5257.80

x y x y x y

SW QUADRANT

1 2 3 4 5 6 7 8

x y x y x y

350.52 5257.80 1051.56 5257.80 1752.6 5257.80 x y x y A

350.52 4556.76 1051.56 4556.76 1752.6 4556.76 2453.64 4556.76 3154.68 4556.76 x y B

350.52 3855.72 1051.56 3855.72 1752.6 3855.72 2453.64 3855.72 3154.68 3855.72 3855.72 3855.72 x y C

350.52 3154.68 1051.56 3154.68 1752.6 3154.68 2453.64 3154.68 3154.68 3154.68 3855.72 3154.68 4556.76 3154.68 D

350.52 2453.64 1051.56 2453.64 1752.6 2453.64 2453.64 2453.64 3154.68 2453.64 3855.72 2453.64 4556.76 2453.64 x y E

350.52 1752.60 1051.56 1752.60 1752.6 1752.60 2453.64 1752.60 3154.68 1752.60 3855.72 1752.60 4556.76 1752.60 5257.8 1752.60 F

350.52 1051.56 1051.56 1051.56 1752.6 1051.56 2453.64 1051.56 3154.68 1051.56 3855.72 1051.56 4556.76 1051.56 5257.8 1051.56 G

350.52 350.52 1051.56 350.52 1752.6 350.52 2453.64 350.52 3154.68 350.52 3855.72 350.52 4556.76 350.52 5257.8 350.52 H

NE QUADRANT

10 119 12 13 14 15 16

350.52 -350.52 1051.56 -350.52 1752.6 -350.52 2453.64 -350.52 3154.68 -350.52 3855.72 -350.52 4556.76 -350.52 5257.8 -350.52 J

350.52 -1051.56 1051.56 -1051.56 1752.6 -1051.56 2453.64 -1051.56 3154.68 -1051.56 3855.72 -1051.56 4556.76 -1051.56 5257.8 -1051.56 K

350.52 -1752.60 1051.56 -1752.60 1752.6 -1752.60 2453.64 -1752.60 3154.68 -1752.60 3855.72 -1752.60 4556.76 -1752.60 5257.8 -1752.60 L

350.52 -2453.64 1051.56 -2453.64 1752.6 -2453.64 2453.64 -2453.64 3154.68 -2453.64 3855.72 -2453.64 4556.76 -2453.64 x y M

350.52 -3154.68 1051.56 -3154.68 1752.6 -3154.68 2453.64 -3154.68 3154.68 -3154.68 3855.72 -3154.68 4556.76 -3154.68 N

350.52 -3855.72 1051.56 -3855.72 1752.6 -3855.72 2453.64 -3855.72 3154.68 -3855.72 3855.72 -3855.72 x y P

350.52 -4556.76 1051.56 -4556.76 1752.6 -4556.76 2453.64 -4556.76 3154.68 -4556.76 x y R

350.52 -5257.80 1051.56 -5257.80 1752.6 -5257.80 x y x y S

x y x y x y

14 15 16

SE QUADRANT

9 10 11 12 13

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Appendix A (continued) – SDU 6 Dose Rate Profile MCNP Models’ Details

Source Volume Determinations

Volumefrustum = (/3)(h)(R2

+ Rr + r2) where h = height

R = larger radiusr = smaller radius

Volumecylinder = (r2)(h) where h = height

r = radius

Conversion: 1 gallon = 3785.412 cc

r (cm) R (cm) h (cm) Vol (cc) Vol (gal) Vol%

Upper Source 3.141593 5729.77 5731.13 50 5158189987

208 Columns 3.141593 30.48 n/a 50 30353805

Upper Subtotal = Upper Source –208 Columns

5127836183 1354631 0.70516967

Lower Source 3.141593 5697.22 5729.77 1199.68 123032590792

Void Core 3.141593 5647.22 5679.77 1199.68 120888650570

Lower Subtotal = Lower Source –Void Core

2143940222 566369 0.29483033

Total =Upper Subtotal+ Lower Subtotal

7271776405 1921000 1.00000000

Page 19: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.19 of 63

Rev.0

Appendix B – SDU 6 Rooftop Penetration MCNP Models’ Details

SDU 6 Rooftop Penetration Model [All Dimensions in centimeters (cm)](NOTE: Not to Scale; Columns not shown for clarity; Upper source only)

SDU 6 Rooftop Penetration Modeling Configurations

Penetration Configuration

Access Hatch(6' x 8')

Open

+ 1/4" Steel Sidewalk Door

+ 1/2" Steel Sidewalk Door

+ 1" Steel Sidewalk Door

+ 2" Steel Sidewalk Door

+ 3" Steel Sidewalk Door

+ 4" Steel Sidewalk Door

+ 1' Concrete Curb & Cover

Active Vent(14" Diam.)

Open

+ 1/4" Steel Cover

Camera Port(12" Diam.)

Open

+ 3.18 cm Steel Victaulic® Cap

+ 1" Steel Cover

+ 1.5" Steel Cover

Drainwater Return Port(36" Diam.)

Open

+ 1/4" Steel Cover

+ 1" Steel Cover

Grout/Inspection Port(3" Diam.)

Open

+ 2.24 cm Steel Victaulic® Cap

Passive Vent(12" Diam.)

Open

+ 1/4" Steel Cover

Thermocouple Port(8" Diam.)

Open

+ 3.02 cm Steel Victaulic® Cap

+ 1/2" Steel Cover

Page 20: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.20 of 63

Rev.0

Appendix B (continued) – SDU 6 Rooftop Penetration MCNP Models’ Details

Source Volume Determinations

Volumefrustum = (/3)(h)(R2

+ Rr + r2) where h = height

R = larger radiusr = smaller radius

Volumecylinder = (r2)(h) where h = height

r = radius

Conversion: 1 gallon = 3785.412 cc

r (cm) R (cm) h (cm) Vol (cc) Vol (gal) Vol%

Upper Source 1 3.141593 5729.77 5730.04 10 1031441772

208 Columns 3.141593 30.48 n/a 10 6070761

Upper Subtotal 1 = Upper Source 1 –208 Columns

1025371011 270874 0.19996173

Upper Source 2 3.141593 5730.04 5730.31 10 1031538980

208 Columns 3.141593 30.48 n/a 10 6070761

Upper Subtotal 2 = Upper Source 2 –208 Columns

1025468219 270900 0.19998069

Upper Source 3 3.141593 5730.31 5730.59 10 1031637993

208 Columns 3.141593 30.48 n/a 10 6070761

Upper Subtotal 3 = Upper Source 3 –208 Columns

1025567232 270926 0.20000000

Upper Source 4 3.141593 5730.59 5730.86 10 1031737010

208 Columns 3.141593 30.48 n/a 10 6070761

Upper Subtotal 4 = Upper Source 4 -208 Columns

1025666249 270952 0.20001931

Upper Source 5 3.141593 5730.86 5731.13 10 1031834232

208 Columns 3.141593 30.48 n/a 10 6070761

Upper Subtotal 5 = Upper Source 5 –208 Columns

1025763471 270978 0.20003827

Total = Sum of Upper Subtotals 1 +2 +3 +4 +5

5127836183 1354631 1.00000000

Page 21: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.21 of 63

Rev.0

Appendix B (continued) – SDU 6 Rooftop Penetration MCNP Models’ Details(Excerpted from Ref. 3.4)

Page 22: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.22 of 63

Rev.0

Appendix B (continued) – SDU 6 Rooftop Penetration MCNP Models’ Details(Excerpted from Ref. 3.4)

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.23 of 63

Rev.0

Appendix C – SDU 6 Transfer Line MCNP Models’ Details

Source Volume Determinations

Volumecylinder = (r2)(l) where l = length

r = radius

Conversion: 1 gallon = 3785.412 cc

r (cm) l (cm) Vol (cc) Vol (gal)

Grout 3.141593 3.9 3046.9 145591.9 38.4613

Leachate 3.141593 2.63 3047.22 66216.34 17.4925

Page 24: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.24 of 63

Rev.0

Appendix D – Example ORIGEN-ARP Input File (015L.inp) for 0.15 Ci/gal DSS

'This SCALE input file was generated by'OrigenArp Version 5.1.01 March 22, 2007#origens0$$ a11 71 e tDecay Case3$$ 21 1 1 0 a16 4 a33 18 e t35$$ 0 t54$$ a8 1 a11 0 e56$$ a2 7 a6 1 a10 0 a13 5 a14 5 a15 3 a17 2 e57** 0 a3 1e-05 e 95$$ 0 t015L0 MTU60** 0.001 0.003 0.01 0.03 0.1 0.3 1 61** f0.05 65$$ 'Gram-Atoms Grams Curies Watts-All Watts-Gamma3z 1 0 0 3z 3z 3z 6z 3z 1 0 0 3z 3z 3z 6z 3z 1 0 0 3z 3z 3z 6z 81$$ 2 0 24 1 e82$$ 2 2 2 2 2 2 2 e83**1.0000000e+07 8.0000000e+06 6.5000000e+06 5.0000000e+06 4.0000000e+063.0000000e+06 2.5000000e+06 2.0000000e+06 1.6600000e+06 1.3300000e+061.0000000e+06 8.0000000e+05 6.0000000e+05 4.0000000e+05 3.0000000e+052.0000000e+05 1.0000000e+05 5.0000000e+04 1.0000000e+04 e73$$ 270600 511250 551340 551370 631540 74** 4.1e-06 3.36e-05 6.9e-05 0.015 6.79e-06 75$$ 1 3 3 3 3 t56$$ 0 0 a10 1 e t 56$$ 0 0 a10 2 e t 56$$ 0 0 a10 3 e t 56$$ 0 0 a10 4 e t 56$$ 0 0 a10 5 e t 56$$ 0 0 a10 6 e t 56$$ 0 0 a10 7 e t 56$$ f0 tend#shellcopy ft71f001 "C:\Documents and Settings\o7882\Desktop\015L.f71"del ft71f001 end

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.25 of 63

Rev.0

Appendix E – Example ORIGEN-ARP Input File (015G.inp) for Grout Made from 0.15 Ci/gal DSS

'This SCALE input file was generated by'OrigenArp Version 5.1.01 March 22, 2007#origens0$$ a11 71 e tDecay Case3$$ 21 1 1 0 a16 4 a33 18 e t35$$ 0 t54$$ a8 1 a11 0 e56$$ a2 7 a6 1 a10 0 a13 5 a14 5 a15 3 a17 2 e57** 0 a3 1e-05 e 95$$ 0 t015G0 MTU60** 0.001 0.003 0.01 0.03 0.1 0.3 1 61** f0.05 65$$ 'Gram-Atoms Grams Curies Watts-All Watts-Gamma3z 1 0 0 3z 3z 3z 6z 3z 1 0 0 3z 3z 3z 6z 3z 1 0 0 3z 3z 3z 6z 81$$ 2 0 24 1 e82$$ 2 2 2 2 2 2 2 e83**1.0000000e+07 8.0000000e+06 6.5000000e+06 5.0000000e+06 4.0000000e+063.0000000e+06 2.5000000e+06 2.0000000e+06 1.6600000e+06 1.3300000e+061.0000000e+06 8.0000000e+05 6.0000000e+05 4.0000000e+05 3.0000000e+052.0000000e+05 1.0000000e+05 5.0000000e+04 1.0000000e+04 e73$$ 270600 511250 551340 551370 631540 74** 2.33e-06 1.91e-05 3.92e-05 0.00852 3.86e-06 75$$ 1 3 3 3 3 t56$$ 0 0 a10 1 e t 56$$ 0 0 a10 2 e t 56$$ 0 0 a10 3 e t 56$$ 0 0 a10 4 e t 56$$ 0 0 a10 5 e t 56$$ 0 0 a10 6 e t 56$$ 0 0 a10 7 e t 56$$ f0 tend#shellcopy ft71f001 "C:\Documents and Settings\o7882\Desktop\015G.f71"del ft71f001 end

Page 26: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.26 of 63

Rev.0

Appendix F – List of MCNP Input and Output Files

File Name File Type File Description

0.0002 Ci/galS60002 Input

SDU6 Dose Rate ProfileS60002o OutputS62OAH Input

Open Access HatchS62OAHo OutputS62AH1 Input

Access Hatch w/ ¼” Steel DoorS62AH1o OutputS62AH2 Input

Access Hatch w/ ½” Steel DoorS62AH2o OutputS62AH3 Input

Access Hatch w/ 1” Steel DoorS62AH3o OutputS62AHC Input Access Hatch w/ 1’ Thick Concrete Cover;

Also Interior Dose Rate 30 cm Above GroutS62AHCo OutputS62OAV Input

Open Active VentS62OAVo Output

S62AV InputActive Vent w/ ¼” Steel Cover

S62AVo OutputS62OCP Input

Open Camera PortS62OCPo OutputS62CP1 Input

Camera Port w/ 3.18 cm Steel Victaulic® CapS62CP1o OutputS62CP2 Input

Camera Port w/ 1” Steel CoverS62CP2o OutputS62CP3 Input

Camera Port w/ 1.5” Steel CoverS62CP3o OutputS62ODW Input

Open Drainwater PortS62ODWo OutputS62DW1 Input

Drainwater Port w/ ¼” Steel CoverS62DW1o OutputS62DW2 Input

Drainwater Port w/ 1” Steel CoverS62DW2o OutputS62OGP Input

Open Grout PortS62OGPo Output

S62GP InputGrout Port w/ 2.24 cm Steel Victaulic® Cap

S62GPo OutputS62OPV Input

Open Passive VentS62OPVo Output

S62PV InputPassive Vent w/ ¼” Steel Cover

S62PVo OutputS62OTC Input

Open Thermocouple PortS62OTCo OutputS62TC1 Input

Thermocouple Port w/ 3.02 cm Steel Victaulic® CapS62TC1o OutputS62TC2 Input

Thermocouple Port w/ ½” Steel CoverS62TC2o OutputLL0002 Input

Leachate LineLL0002o OutputGL0002 Input

Grout LineGL0002o Output

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.27 of 63

Rev.0

Appendix F (continued) – List of MCNP Input and Output Files

File Name File Type File Description

0.006 Ci/galS6006 Input

SDU6 Dose Rate ProfileS6006o OutputS66OAH Input

Open Access HatchS66OAHo OutputS66AH1 Input

Access Hatch w/ ¼” Steel DoorS66AH1o OutputS66AH2 Input

Access Hatch w/ ½” Steel DoorS66AH2o OutputS66AH3 Input

Access Hatch w/ 1” Steel DoorS66AH3o OutputS66AH4 Input

Access Hatch w/ 2” Steel DoorS66AH4o OutputS66AH5 Input

Access Hatch w/ 4” Steel DoorS66AH5o OutputS66AH6 Input

Access Hatch w/ 4” Steel DoorS66AH6o OutputS66AHC Input Access Hatch w/ 1’ Thick Concrete Cover;

Also Interior Dose Rate 30 cm Above GroutS66AHCo OutputS66OAV Input

Open Active VentS66OAVo Output

S66AV InputActive Vent w/ ¼” Steel Cover

S66AVo OutputS66OCP Input

Open Camera PortS66OCPo OutputS66CP1 Input

Camera Port w/ 3.18 cm Steel Victaulic® CapS66CP1o OutputS66CP2 Input

Camera Port w/ 1” Steel CoverS66CP2o OutputS66CP3 Input

Camera Port w/ 1.5” Steel CoverS66CP3o OutputS66ODW Input

Open Drainwater PortS66ODWo OutputS66DW1 Input

Drainwater Port w/ ¼” Steel CoverS66DW1o OutputS66DW2 Input

Drainwater Port w/ 1” Steel CoverS66DW2o OutputS66OGP Input

Open Grout PortS66OGPo Output

S66GP InputGrout Port w/ 2.24 cm Steel Victaulic® Cap

S66GPo OutputS66OPV Input

Open Passive VentS66OPVo Output

S66PV InputPassive Vent w/ ¼” Steel Cover

S66PVo OutputS66OTC Input

Open Thermocouple PortS66OTCo OutputS66TC1 Input

Thermocouple Port w/ 3.02 cm Steel Victaulic® CapS66TC1o OutputS66TC2 Input

Thermocouple Port w/ ½” Steel CoverS66TC2o Output

LL006 InputLeachate Line

LL006o OutputGL006 Input

Grout LineGL006o Output

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Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.28 of 63

Rev.0

Appendix F (continued) – List of MCNP Input and Output Files

File Name File Type File Description

0.015 Ci/galS6015N Input

SDU6 Dose Rate Profile – NearS6015No OutputS6015F Input

SDU6 Dose Rate Profile – FarS6015Fo OutputS15OAH Input

Open Access HatchS15OAHo OutputS15AH1 Input

Access Hatch w/ ¼” Steel DoorS15AH1o OutputS15AH2 Input

Access Hatch w/ ½” Steel DoorS15AH2o OutputS15AH3 Input

Access Hatch w/ 1” Steel DoorS15AH3o OutputS15AH4 Input

Access Hatch w/ 2” Steel DoorS15AH4o OutputS15AH5 Input

Access Hatch w/ 4” Steel DoorS15AH5o OutputS15AH6 Input

Access Hatch w/ 4” Steel DoorS15AH6o OutputS15AHC Input Access Hatch w/ 1’ Thick Concrete Cover;

Also Interior Dose Rate 30 cm Above GroutS15AHCo OutputS15OAV Input

Open Active VentS15OAVo Output

S15AV InputActive Vent w/ ¼” Steel Cover

S15AVo OutputS15OCP Input

Open Camera PortS15OCPo OutputS15CP1 Input

Camera Port w/ 3.18 cm Steel Victaulic® CapS15CP1o OutputS15CP2 Input

Camera Port w/ 1” Steel CoverS15CP2o OutputS15CP3 Input

Camera Port w/ 1.5” Steel CoverS15CP3o OutputS15ODW Input

Open Drainwater PortS15ODWo OutputS15DW1 Input

Drainwater Port w/ ¼” Steel CoverS15DW1o OutputS15DW2 Input

Drainwater Port w/ 1” Steel CoverS15DW2o OutputS15OGP Input

Open Grout PortS15OGPo Output

S15GP InputGrout Port w/ 2.24 cm Steel Victaulic® Cap

S15GPo OutputS15OPV Input

Open Passive VentS15OPVo Output

S15PV InputPassive Vent w/ ¼” Steel Cover

S15PVo OutputS15OTC Input

Open Thermocouple PortS15OTCo OutputS15TC1 Input

Thermocouple Port w/ 3.02 cm Steel Victaulic® CapS15TC1o OutputS15TC2 Input

Thermocouple Port w/ ½” Steel CoverS15TC2o Output

LL015 InputLeachate Line

LL015o OutputGL015 Input

Grout LineGL015o Output

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Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.29 of 63

Rev.0

Appendix F (continued) – List of MCNP Input and Output Files

File Name File Type File Description

0.03 Ci/galS603N Input

SDU6 Dose Rate Profile – NearS603No OutputS603F Input

SDU6 Dose Rate Profile – FarS603Fo OutputS63OAH Input

Open Access HatchS63OAHo OutputS63AH1 Input

Access Hatch w/ ¼” Steel DoorS63AH1o OutputS63AH2 Input

Access Hatch w/ ½” Steel DoorS63AH2o OutputS63AH3 Input

Access Hatch w/ 1” Steel DoorS63AH3o OutputS63AH4 Input

Access Hatch w/ 2” Steel DoorS63AH4o OutputS63AH5 Input

Access Hatch w/ 4” Steel DoorS63AH5o OutputS63AH6 Input

Access Hatch w/ 4” Steel DoorS63AH6o OutputS63AHC Input Access Hatch w/ 1’ Thick Concrete Cover;

Also Interior Dose Rate 30 cm Above GroutS63AHCo OutputS63OAV Input

Open Active VentS63OAVo Output

S63AV InputActive Vent w/ ¼” Steel Cover

S63AVo OutputS63OCP Input

Open Camera PortS63OCPo OutputS63CP1 Input

Camera Port w/ 3.18 cm Steel Victaulic® CapS63CP1o OutputS63CP2 Input

Camera Port w/ 1” Steel CoverS63CP2o OutputS63CP3 Input

Camera Port w/ 1.5” Steel CoverS63CP3o OutputS63ODW Input

Open Drainwater PortS63ODWo OutputS63DW1 Input

Drainwater Port w/ ¼” Steel CoverS63DW1o OutputS63DW2 Input

Drainwater Port w/ 1” Steel CoverS63DW2o OutputS63OGP Input

Open Grout PortS63OGPo Output

S63GP InputGrout Port w/ 2.24 cm Steel Victaulic® Cap

S63GPo OutputS63OPV Input

Open Passive VentS63OPVo Output

S63PV InputPassive Vent w/ ¼” Steel Cover

S63PVo OutputS63OTC Input

Open Thermocouple PortS63OTCo OutputS63TC1 Input

Thermocouple Port w/ 3.02 cm Steel Victaulic® CapS63TC1o OutputS63TC2 Input

Thermocouple Port w/ ½” Steel CoverS63TC2o Output

LL03 InputLeachate Line

LL03o OutputGL03 Input

Grout LineGL03o Output

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.30 of 63

Rev.0

Appendix G – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

SDU6 DOSE RATE PROFILE (0.015 Ci/gal)cc **************************************************************************c * NOTES: *c **************************************************************************c * *c * 1. Tank ID = 375' Average. Tank height = 43'. *c * *c * 2. Core wall tapers from 10" top to 24" bottom; roof 12" thick. *c * 208 interior columns (23' x 23' grid). SDU modeled above grade. *c * *c * 3. Filled to 41' w/ grout from 0.015 Ci/gal DSS (i.e., revised *c * Cs-137 concentration per X-ESR-H-00456) leaving 2' vapor space. *c * *c * 4. Dose rate profile from 30 cm to 180' from SDU perimeter in 10' *c * increments at 4', 10', 20', 30' and 40' above grade using RCC *c * detectors. Also, dose rates @ 30 cm above tank top. *c * *c **************************************************************************cc CELL CARDSc1 0 -1 imp:p=0 $Core (Void)2 1 -1.7007 1 -2 imp:p=1 $Lower Source (Grout)3 1 -1.7007 -3 101 206I 308 imp:p=1 $Upper Source (Grout)4 2 -0.001205 -4 101 206I 308 imp:p=7 $Vapor Space (Air)5 3 -2.3 2 3 4 -5 imp:p=8 $Wall 1 (Cement)6 3 -2.3 5 -6 imp:p=37 $Wall 2 (Cement)7 3 -2.3 6 -7 imp:p=156 $Wall 3 (Cement)8 3 -2.3 7 -8 imp:p=645 $Wall 4 (Cement)9 3 -2.3 -9 imp:p=9 $Roof 110 3 -2.3 -10 imp:p=38 $Roof 211 3 -2.3 -11 imp:p=185 $Roof 312 2 -0.001205 8 9 10 11 14 -17 401 98I 500 imp:p=776 $Atmosphere13 0 -16 imp:p=0 $Slab14 0 -14 15 16 -17 imp:p=0 $Soil15 0 (-15 -17):17 imp:p=0 $Universec NW QUADRANT INTERIOR COLUMNS----------------------------------------------101 3 -2.3 -12 13 -101 imp:p=7102 3 -2.3 -12 13 -102 imp:p=7103 3 -2.3 -12 13 -103 imp:p=7104 3 -2.3 -12 13 -104 imp:p=7105 3 -2.3 -12 13 -105 imp:p=7106 3 -2.3 -12 13 -106 imp:p=7107 3 -2.3 -12 13 -107 imp:p=7108 3 -2.3 -12 13 -108 imp:p=7109 3 -2.3 -12 13 -109 imp:p=7110 3 -2.3 -12 13 -110 imp:p=7111 3 -2.3 -12 13 -111 imp:p=7112 3 -2.3 -12 13 -112 imp:p=7113 3 -2.3 -12 13 -113 imp:p=7114 3 -2.3 -12 13 -114 imp:p=7115 3 -2.3 -12 13 -115 imp:p=7116 3 -2.3 -12 13 -116 imp:p=7117 3 -2.3 -12 13 -117 imp:p=7118 3 -2.3 -12 13 -118 imp:p=7119 3 -2.3 -12 13 -119 imp:p=7120 3 -2.3 -12 13 -120 imp:p=7121 3 -2.3 -12 13 -121 imp:p=7122 3 -2.3 -12 13 -122 imp:p=7123 3 -2.3 -12 13 -123 imp:p=7124 3 -2.3 -12 13 -124 imp:p=7125 3 -2.3 -12 13 -125 imp:p=7126 3 -2.3 -12 13 -126 imp:p=7127 3 -2.3 -12 13 -127 imp:p=7128 3 -2.3 -12 13 -128 imp:p=7129 3 -2.3 -12 13 -129 imp:p=7

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.31 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

130 3 -2.3 -12 13 -130 imp:p=7131 3 -2.3 -12 13 -131 imp:p=7132 3 -2.3 -12 13 -132 imp:p=7133 3 -2.3 -12 13 -133 imp:p=7134 3 -2.3 -12 13 -134 imp:p=7135 3 -2.3 -12 13 -135 imp:p=7136 3 -2.3 -12 13 -136 imp:p=7137 3 -2.3 -12 13 -137 imp:p=7138 3 -2.3 -12 13 -138 imp:p=7139 3 -2.3 -12 13 -139 imp:p=7140 3 -2.3 -12 13 -140 imp:p=7141 3 -2.3 -12 13 -141 imp:p=7142 3 -2.3 -12 13 -142 imp:p=7143 3 -2.3 -12 13 -143 imp:p=7144 3 -2.3 -12 13 -144 imp:p=7145 3 -2.3 -12 13 -145 imp:p=7146 3 -2.3 -12 13 -146 imp:p=7147 3 -2.3 -12 13 -147 imp:p=7148 3 -2.3 -12 13 -148 imp:p=7149 3 -2.3 -12 13 -149 imp:p=7150 3 -2.3 -12 13 -150 imp:p=7151 3 -2.3 -12 13 -151 imp:p=7152 3 -2.3 -12 13 -152 imp:p=7c NE QUADRANT INTERIOR COLUMNS----------------------------------------------153 3 -2.3 -12 13 -153 imp:p=7154 3 -2.3 -12 13 -154 imp:p=7155 3 -2.3 -12 13 -155 imp:p=7156 3 -2.3 -12 13 -156 imp:p=7157 3 -2.3 -12 13 -157 imp:p=7158 3 -2.3 -12 13 -158 imp:p=7159 3 -2.3 -12 13 -159 imp:p=7160 3 -2.3 -12 13 -160 imp:p=7161 3 -2.3 -12 13 -161 imp:p=7162 3 -2.3 -12 13 -162 imp:p=7163 3 -2.3 -12 13 -163 imp:p=7164 3 -2.3 -12 13 -164 imp:p=7165 3 -2.3 -12 13 -165 imp:p=7166 3 -2.3 -12 13 -166 imp:p=7167 3 -2.3 -12 13 -167 imp:p=7168 3 -2.3 -12 13 -168 imp:p=7169 3 -2.3 -12 13 -169 imp:p=7170 3 -2.3 -12 13 -170 imp:p=7171 3 -2.3 -12 13 -171 imp:p=7172 3 -2.3 -12 13 -172 imp:p=7173 3 -2.3 -12 13 -173 imp:p=7174 3 -2.3 -12 13 -174 imp:p=7175 3 -2.3 -12 13 -175 imp:p=7176 3 -2.3 -12 13 -176 imp:p=7177 3 -2.3 -12 13 -177 imp:p=7178 3 -2.3 -12 13 -178 imp:p=7179 3 -2.3 -12 13 -179 imp:p=7180 3 -2.3 -12 13 -180 imp:p=7181 3 -2.3 -12 13 -181 imp:p=7182 3 -2.3 -12 13 -182 imp:p=7183 3 -2.3 -12 13 -183 imp:p=7184 3 -2.3 -12 13 -184 imp:p=7185 3 -2.3 -12 13 -185 imp:p=7186 3 -2.3 -12 13 -186 imp:p=7187 3 -2.3 -12 13 -187 imp:p=7188 3 -2.3 -12 13 -188 imp:p=7189 3 -2.3 -12 13 -189 imp:p=7190 3 -2.3 -12 13 -190 imp:p=7191 3 -2.3 -12 13 -191 imp:p=7192 3 -2.3 -12 13 -192 imp:p=7193 3 -2.3 -12 13 -193 imp:p=7194 3 -2.3 -12 13 -194 imp:p=7195 3 -2.3 -12 13 -195 imp:p=7196 3 -2.3 -12 13 -196 imp:p=7

Page 32: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.32 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

197 3 -2.3 -12 13 -197 imp:p=7198 3 -2.3 -12 13 -198 imp:p=7199 3 -2.3 -12 13 -199 imp:p=7200 3 -2.3 -12 13 -200 imp:p=7201 3 -2.3 -12 13 -201 imp:p=7202 3 -2.3 -12 13 -202 imp:p=7203 3 -2.3 -12 13 -203 imp:p=7204 3 -2.3 -12 13 -204 imp:p=7c SE QUADRANT INTERIOR COLUMNS----------------------------------------------205 3 -2.3 -12 13 -205 imp:p=7206 3 -2.3 -12 13 -206 imp:p=7207 3 -2.3 -12 13 -207 imp:p=7208 3 -2.3 -12 13 -208 imp:p=7209 3 -2.3 -12 13 -209 imp:p=7210 3 -2.3 -12 13 -210 imp:p=7211 3 -2.3 -12 13 -211 imp:p=7212 3 -2.3 -12 13 -212 imp:p=7213 3 -2.3 -12 13 -213 imp:p=7214 3 -2.3 -12 13 -214 imp:p=7215 3 -2.3 -12 13 -215 imp:p=7216 3 -2.3 -12 13 -216 imp:p=7217 3 -2.3 -12 13 -217 imp:p=7218 3 -2.3 -12 13 -218 imp:p=7219 3 -2.3 -12 13 -219 imp:p=7220 3 -2.3 -12 13 -220 imp:p=7221 3 -2.3 -12 13 -221 imp:p=7222 3 -2.3 -12 13 -222 imp:p=7223 3 -2.3 -12 13 -223 imp:p=7224 3 -2.3 -12 13 -224 imp:p=7225 3 -2.3 -12 13 -225 imp:p=7226 3 -2.3 -12 13 -226 imp:p=7227 3 -2.3 -12 13 -227 imp:p=7228 3 -2.3 -12 13 -228 imp:p=7229 3 -2.3 -12 13 -229 imp:p=7230 3 -2.3 -12 13 -230 imp:p=7231 3 -2.3 -12 13 -231 imp:p=7232 3 -2.3 -12 13 -232 imp:p=7233 3 -2.3 -12 13 -233 imp:p=7234 3 -2.3 -12 13 -234 imp:p=7235 3 -2.3 -12 13 -235 imp:p=7236 3 -2.3 -12 13 -236 imp:p=7237 3 -2.3 -12 13 -237 imp:p=7238 3 -2.3 -12 13 -238 imp:p=7239 3 -2.3 -12 13 -239 imp:p=7240 3 -2.3 -12 13 -240 imp:p=7241 3 -2.3 -12 13 -241 imp:p=7242 3 -2.3 -12 13 -242 imp:p=7243 3 -2.3 -12 13 -243 imp:p=7244 3 -2.3 -12 13 -244 imp:p=7245 3 -2.3 -12 13 -245 imp:p=7246 3 -2.3 -12 13 -246 imp:p=7247 3 -2.3 -12 13 -247 imp:p=7248 3 -2.3 -12 13 -248 imp:p=7249 3 -2.3 -12 13 -249 imp:p=7250 3 -2.3 -12 13 -250 imp:p=7251 3 -2.3 -12 13 -251 imp:p=7252 3 -2.3 -12 13 -252 imp:p=7253 3 -2.3 -12 13 -253 imp:p=7254 3 -2.3 -12 13 -254 imp:p=7255 3 -2.3 -12 13 -255 imp:p=7256 3 -2.3 -12 13 -256 imp:p=7c SW QUADRANT INTERIOR COLUMNS----------------------------------------------257 3 -2.3 -12 13 -257 imp:p=7258 3 -2.3 -12 13 -258 imp:p=7259 3 -2.3 -12 13 -259 imp:p=7260 3 -2.3 -12 13 -260 imp:p=7261 3 -2.3 -12 13 -261 imp:p=7262 3 -2.3 -12 13 -262 imp:p=7

Page 33: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.33 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

263 3 -2.3 -12 13 -263 imp:p=7264 3 -2.3 -12 13 -264 imp:p=7265 3 -2.3 -12 13 -265 imp:p=7266 3 -2.3 -12 13 -266 imp:p=7267 3 -2.3 -12 13 -267 imp:p=7268 3 -2.3 -12 13 -268 imp:p=7269 3 -2.3 -12 13 -269 imp:p=7270 3 -2.3 -12 13 -270 imp:p=7271 3 -2.3 -12 13 -271 imp:p=7272 3 -2.3 -12 13 -272 imp:p=7273 3 -2.3 -12 13 -273 imp:p=7274 3 -2.3 -12 13 -274 imp:p=7275 3 -2.3 -12 13 -275 imp:p=7276 3 -2.3 -12 13 -276 imp:p=7277 3 -2.3 -12 13 -277 imp:p=7278 3 -2.3 -12 13 -278 imp:p=7279 3 -2.3 -12 13 -279 imp:p=7280 3 -2.3 -12 13 -280 imp:p=7281 3 -2.3 -12 13 -281 imp:p=7282 3 -2.3 -12 13 -282 imp:p=7283 3 -2.3 -12 13 -283 imp:p=7284 3 -2.3 -12 13 -284 imp:p=7285 3 -2.3 -12 13 -285 imp:p=7286 3 -2.3 -12 13 -286 imp:p=7287 3 -2.3 -12 13 -287 imp:p=7288 3 -2.3 -12 13 -288 imp:p=7289 3 -2.3 -12 13 -289 imp:p=7290 3 -2.3 -12 13 -290 imp:p=7291 3 -2.3 -12 13 -291 imp:p=7292 3 -2.3 -12 13 -292 imp:p=7293 3 -2.3 -12 13 -293 imp:p=7294 3 -2.3 -12 13 -294 imp:p=7295 3 -2.3 -12 13 -295 imp:p=7296 3 -2.3 -12 13 -296 imp:p=7297 3 -2.3 -12 13 -297 imp:p=7298 3 -2.3 -12 13 -298 imp:p=7299 3 -2.3 -12 13 -299 imp:p=7300 3 -2.3 -12 13 -300 imp:p=7301 3 -2.3 -12 13 -301 imp:p=7302 3 -2.3 -12 13 -302 imp:p=7303 3 -2.3 -12 13 -303 imp:p=7304 3 -2.3 -12 13 -304 imp:p=7305 3 -2.3 -12 13 -305 imp:p=7306 3 -2.3 -12 13 -306 imp:p=7307 3 -2.3 -12 13 -307 imp:p=7308 3 -2.3 -12 13 -308 imp:p=7c VOLUME DETECTORS 30 CM ABOVE ROOF401 2 -0.001205 -401 imp:p=776402 2 -0.001205 401 -402 imp:p=776403 2 -0.001205 402 -403 imp:p=776404 2 -0.001205 403 -404 imp:p=776405 2 -0.001205 -405 imp:p=776c VOLUME DETECTORS RADIALLY AROUND SDU @ 4' ABOVE GROUND406 2 -0.001205 -406 imp:p=6208407 2 -0.001205 -407 imp:p=6208408 2 -0.001205 -408 imp:p=6208409 2 -0.001205 -409 imp:p=6208410 2 -0.001205 -410 imp:p=6208411 2 -0.001205 -411 imp:p=6208412 2 -0.001205 -412 imp:p=6208413 2 -0.001205 -413 imp:p=6208414 2 -0.001205 -414 imp:p=6208415 2 -0.001205 -415 imp:p=6208416 2 -0.001205 -416 imp:p=6208417 2 -0.001205 -417 imp:p=6208418 2 -0.001205 -418 imp:p=6208419 2 -0.001205 -419 imp:p=6208420 2 -0.001205 -420 imp:p=6208

Page 34: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.34 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

421 2 -0.001205 -421 imp:p=6208422 2 -0.001205 -422 imp:p=6208423 2 -0.001205 -423 imp:p=6208424 2 -0.001205 -424 imp:p=6208c VOLUME DETECTORS RADIALLY AROUND SDU @ 10' ABOVE GROUND425 2 -0.001205 -425 imp:p=6208426 2 -0.001205 -426 imp:p=6208427 2 -0.001205 -427 imp:p=6208428 2 -0.001205 -428 imp:p=6208429 2 -0.001205 -429 imp:p=6208430 2 -0.001205 -430 imp:p=6208431 2 -0.001205 -431 imp:p=6208432 2 -0.001205 -432 imp:p=6208433 2 -0.001205 -433 imp:p=6208434 2 -0.001205 -434 imp:p=6208435 2 -0.001205 -435 imp:p=6208436 2 -0.001205 -436 imp:p=6208437 2 -0.001205 -437 imp:p=6208438 2 -0.001205 -438 imp:p=6208439 2 -0.001205 -439 imp:p=6208440 2 -0.001205 -440 imp:p=6208441 2 -0.001205 -441 imp:p=6208442 2 -0.001205 -442 imp:p=6208443 2 -0.001205 -443 imp:p=6208c VOLUME DETECTORS RADIALLY AROUND SDU @ 20' ABOVE GROUND444 2 -0.001205 -444 imp:p=6208445 2 -0.001205 -445 imp:p=6208446 2 -0.001205 -446 imp:p=6208447 2 -0.001205 -447 imp:p=6208448 2 -0.001205 -448 imp:p=6208449 2 -0.001205 -449 imp:p=6208450 2 -0.001205 -450 imp:p=6208451 2 -0.001205 -451 imp:p=6208452 2 -0.001205 -452 imp:p=6208453 2 -0.001205 -453 imp:p=6208454 2 -0.001205 -454 imp:p=6208455 2 -0.001205 -455 imp:p=6208456 2 -0.001205 -456 imp:p=6208457 2 -0.001205 -457 imp:p=6208458 2 -0.001205 -458 imp:p=6208459 2 -0.001205 -459 imp:p=6208460 2 -0.001205 -460 imp:p=6208461 2 -0.001205 -461 imp:p=6208462 2 -0.001205 -462 imp:p=6208c VOLUME DETECTORS RADIALLY AROUND SDU @ 30' ABOVE GROUND463 2 -0.001205 -463 imp:p=6208464 2 -0.001205 -464 imp:p=6208465 2 -0.001205 -465 imp:p=6208466 2 -0.001205 -466 imp:p=6208467 2 -0.001205 -467 imp:p=6208468 2 -0.001205 -468 imp:p=6208469 2 -0.001205 -469 imp:p=6208470 2 -0.001205 -470 imp:p=6208471 2 -0.001205 -471 imp:p=6208472 2 -0.001205 -472 imp:p=6208473 2 -0.001205 -473 imp:p=6208474 2 -0.001205 -474 imp:p=6208475 2 -0.001205 -475 imp:p=6208476 2 -0.001205 -476 imp:p=6208477 2 -0.001205 -477 imp:p=6208478 2 -0.001205 -478 imp:p=6208479 2 -0.001205 -479 imp:p=6208480 2 -0.001205 -480 imp:p=6208481 2 -0.001205 -481 imp:p=6208c VOLUME DETECTORS RADIALLY AROUND SDU @ 40' ABOVE GROUND482 2 -0.001205 -482 imp:p=6208483 2 -0.001205 -483 imp:p=6208484 2 -0.001205 -484 imp:p=6208

Page 35: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.35 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

485 2 -0.001205 -485 imp:p=6208486 2 -0.001205 -486 imp:p=6208487 2 -0.001205 -487 imp:p=6208488 2 -0.001205 -488 imp:p=6208489 2 -0.001205 -489 imp:p=6208490 2 -0.001205 -490 imp:p=6208491 2 -0.001205 -491 imp:p=6208492 2 -0.001205 -492 imp:p=6208493 2 -0.001205 -493 imp:p=6208494 2 -0.001205 -494 imp:p=6208495 2 -0.001205 -495 imp:p=6208496 2 -0.001205 -496 imp:p=6208497 2 -0.001205 -497 imp:p=6208498 2 -0.001205 -498 imp:p=6208499 2 -0.001205 -499 imp:p=6208500 2 -0.001205 -500 imp:p=6208

c SURFACE CARDSc1 trc 0 0 0.00 0 0 1199.68 5647.22 5679.77 $Core2 trc 0 0 0.00 0 0 1199.68 5697.22 5729.77 $Lower Source3 trc 0 0 1199.68 0 0 50.00 5729.77 5731.13 $Upper Source4 trc 0 0 1249.68 0 0 60.96 5731.13 5732.78 $Vapor Space5 trc 0 0 0.00 0 0 1310.64 5712.46 5739.13 $Wall 16 trc 0 0 0.00 0 0 1310.64 5727.70 5745.48 $Wall 27 trc 0 0 0.00 0 0 1310.64 5742.94 5751.83 $Wall 38 rcc 0 0 0.00 0 0 1310.64 5758.18 $Wall 49 rcc 0 0 1310.64 0 0 10.16 5786.12 $Roof 110 rcc 0 0 1320.80 0 0 10.16 5786.12 $Roof 211 rcc 0 0 1330.96 0 0 10.16 5786.12 $Roof 312 pz 1310.64 $Roof Btm13 pz 1199.68 $Upper Source Btm14 pz 0 $Soil Top15 pz -60.96 $Soil Bottom16 rcc 0 0 0 0 0 -60.96 5819.08 $Slab17 sz -15000 37000 $Problem Boundaryc NW QUADRANT INTERIOR COLUMNS----------------------------------------------101 c/z -350.52 350.52 30.48102 c/z -1051.56 350.52 30.48103 c/z -1752.60 350.52 30.48104 c/z -2453.64 350.52 30.48105 c/z -3154.68 350.52 30.48106 c/z -3855.72 350.52 30.48107 c/z -4556.76 350.52 30.48108 c/z -5257.80 350.52 30.48109 c/z -350.52 1051.56 30.48110 c/z -1051.56 1051.56 30.48111 c/z -1752.60 1051.56 30.48112 c/z -2453.64 1051.56 30.48113 c/z -3154.68 1051.56 30.48114 c/z -3855.72 1051.56 30.48115 c/z -4556.76 1051.56 30.48116 c/z -5257.80 1051.56 30.48117 c/z -350.52 1752.60 30.48118 c/z -1051.56 1752.60 30.48119 c/z -1752.60 1752.60 30.48120 c/z -2453.64 1752.60 30.48121 c/z -3154.68 1752.60 30.48122 c/z -3855.72 1752.60 30.48123 c/z -4556.76 1752.60 30.48124 c/z -5257.80 1752.60 30.48125 c/z -350.52 2453.64 30.48126 c/z -1051.56 2453.64 30.48127 c/z -1752.60 2453.64 30.48128 c/z -2453.64 2453.64 30.48129 c/z -3154.68 2453.64 30.48130 c/z -3855.72 2453.64 30.48131 c/z -4556.76 2453.64 30.48

Page 36: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.36 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

132 c/z -350.52 3154.68 30.48133 c/z -1051.56 3154.68 30.48134 c/z -1752.60 3154.68 30.48135 c/z -2453.64 3154.68 30.48136 c/z -3154.68 3154.68 30.48137 c/z -3855.72 3154.68 30.48138 c/z -4556.76 3154.68 30.48139 c/z -350.52 3855.72 30.48140 c/z -1051.56 3855.72 30.48141 c/z -1752.60 3855.72 30.48142 c/z -2453.64 3855.72 30.48143 c/z -3154.68 3855.72 30.48144 c/z -3855.72 3855.72 30.48145 c/z -350.52 4556.76 30.48146 c/z -1051.56 4556.76 30.48147 c/z -1752.60 4556.76 30.48148 c/z -2453.64 4556.76 30.48149 c/z -3154.68 4556.76 30.48150 c/z -350.52 5257.80 30.48151 c/z -1051.56 5257.80 30.48152 c/z -1752.60 5257.80 30.48c NE QUADRANT INTERIOR COLUMNS----------------------------------------------153 c/z 350.52 350.52 30.48154 c/z 1051.56 350.52 30.48155 c/z 1752.60 350.52 30.48156 c/z 2453.64 350.52 30.48157 c/z 3154.68 350.52 30.48158 c/z 3855.72 350.52 30.48159 c/z 4556.76 350.52 30.48160 c/z 5257.80 350.52 30.48161 c/z 350.52 1051.56 30.48162 c/z 1051.56 1051.56 30.48163 c/z 1752.60 1051.56 30.48164 c/z 2453.64 1051.56 30.48165 c/z 3154.68 1051.56 30.48166 c/z 3855.72 1051.56 30.48167 c/z 4556.76 1051.56 30.48168 c/z 5257.80 1051.56 30.48169 c/z 350.52 1752.60 30.48170 c/z 1051.56 1752.60 30.48171 c/z 1752.60 1752.60 30.48172 c/z 2453.64 1752.60 30.48173 c/z 3154.68 1752.60 30.48174 c/z 3855.72 1752.60 30.48175 c/z 4556.76 1752.60 30.48176 c/z 5257.80 1752.60 30.48177 c/z 350.52 2453.64 30.48178 c/z 1051.56 2453.64 30.48179 c/z 1752.60 2453.64 30.48180 c/z 2453.64 2453.64 30.48181 c/z 3154.68 2453.64 30.48182 c/z 3855.72 2453.64 30.48183 c/z 4556.76 2453.64 30.48184 c/z 350.52 3154.68 30.48185 c/z 1051.56 3154.68 30.48186 c/z 1752.60 3154.68 30.48187 c/z 2453.64 3154.68 30.48188 c/z 3154.68 3154.68 30.48189 c/z 3855.72 3154.68 30.48190 c/z 4556.76 3154.68 30.48191 c/z 350.52 3855.72 30.48192 c/z 1051.56 3855.72 30.48193 c/z 1752.60 3855.72 30.48194 c/z 2453.64 3855.72 30.48195 c/z 3154.68 3855.72 30.48196 c/z 3855.72 3855.72 30.48197 c/z 350.52 4556.76 30.48198 c/z 1051.56 4556.76 30.48

Page 37: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.37 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

199 c/z 1752.60 4556.76 30.48200 c/z 2453.64 4556.76 30.48201 c/z 3154.68 4556.76 30.48202 c/z 350.52 5257.80 30.48203 c/z 1051.56 5257.80 30.48204 c/z 1752.60 5257.80 30.48c SE QUADRANT INTERIOR COLUMNS----------------------------------------------205 c/z 350.52 -350.52 30.48206 c/z 1051.56 -350.52 30.48207 c/z 1752.60 -350.52 30.48208 c/z 2453.64 -350.52 30.48209 c/z 3154.68 -350.52 30.48210 c/z 3855.72 -350.52 30.48211 c/z 4556.76 -350.52 30.48212 c/z 5257.80 -350.52 30.48213 c/z 350.52 -1051.56 30.48214 c/z 1051.56 -1051.56 30.48215 c/z 1752.60 -1051.56 30.48216 c/z 2453.64 -1051.56 30.48217 c/z 3154.68 -1051.56 30.48218 c/z 3855.72 -1051.56 30.48219 c/z 4556.76 -1051.56 30.48220 c/z 5257.80 -1051.56 30.48221 c/z 350.52 -1752.60 30.48222 c/z 1051.56 -1752.60 30.48223 c/z 1752.60 -1752.60 30.48224 c/z 2453.64 -1752.60 30.48225 c/z 3154.68 -1752.60 30.48226 c/z 3855.72 -1752.60 30.48227 c/z 4556.76 -1752.60 30.48228 c/z 5257.80 -1752.60 30.48229 c/z 350.52 -2453.64 30.48230 c/z 1051.56 -2453.64 30.48231 c/z 1752.60 -2453.64 30.48232 c/z 2453.64 -2453.64 30.48233 c/z 3154.68 -2453.64 30.48234 c/z 3855.72 -2453.64 30.48235 c/z 4556.76 -2453.64 30.48236 c/z 350.52 -3154.68 30.48237 c/z 1051.56 -3154.68 30.48238 c/z 1752.60 -3154.68 30.48239 c/z 2453.64 -3154.68 30.48240 c/z 3154.68 -3154.68 30.48241 c/z 3855.72 -3154.68 30.48242 c/z 4556.76 -3154.68 30.48243 c/z 350.52 -3855.72 30.48244 c/z 1051.56 -3855.72 30.48245 c/z 1752.60 -3855.72 30.48246 c/z 2453.64 -3855.72 30.48247 c/z 3154.68 -3855.72 30.48248 c/z 3855.72 -3855.72 30.48249 c/z 350.52 -4556.76 30.48250 c/z 1051.56 -4556.76 30.48251 c/z 1752.60 -4556.76 30.48252 c/z 2453.64 -4556.76 30.48253 c/z 3154.68 -4556.76 30.48254 c/z 350.52 -5257.80 30.48255 c/z 1051.56 -5257.80 30.48256 c/z 1752.60 -5257.80 30.48c SW QUADRANT INTERIOR COLUMNS----------------------------------------------257 c/z -350.52 -350.52 30.48258 c/z -1051.56 -350.52 30.48259 c/z -1752.60 -350.52 30.48260 c/z -2453.64 -350.52 30.48261 c/z -3154.68 -350.52 30.48262 c/z -3855.72 -350.52 30.48263 c/z -4556.76 -350.52 30.48264 c/z -5257.80 -350.52 30.48

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.38 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

265 c/z -350.52 -1051.56 30.48266 c/z -1051.56 -1051.56 30.48267 c/z -1752.60 -1051.56 30.48268 c/z -2453.64 -1051.56 30.48269 c/z -3154.68 -1051.56 30.48270 c/z -3855.72 -1051.56 30.48271 c/z -4556.76 -1051.56 30.48272 c/z -5257.80 -1051.56 30.48273 c/z -350.52 -1752.60 30.48274 c/z -1051.56 -1752.60 30.48275 c/z -1752.60 -1752.60 30.48276 c/z -2453.64 -1752.60 30.48277 c/z -3154.68 -1752.60 30.48278 c/z -3855.72 -1752.60 30.48279 c/z -4556.76 -1752.60 30.48280 c/z -5257.80 -1752.60 30.48281 c/z -350.52 -2453.64 30.48282 c/z -1051.56 -2453.64 30.48283 c/z -1752.60 -2453.64 30.48284 c/z -2453.64 -2453.64 30.48285 c/z -3154.68 -2453.64 30.48286 c/z -3855.72 -2453.64 30.48287 c/z -4556.76 -2453.64 30.48288 c/z -350.52 -3154.68 30.48289 c/z -1051.56 -3154.68 30.48290 c/z -1752.60 -3154.68 30.48291 c/z -2453.64 -3154.68 30.48292 c/z -3154.68 -3154.68 30.48293 c/z -3855.72 -3154.68 30.48294 c/z -4556.76 -3154.68 30.48295 c/z -350.52 -3855.72 30.48296 c/z -1051.56 -3855.72 30.48297 c/z -1752.60 -3855.72 30.48298 c/z -2453.64 -3855.72 30.48299 c/z -3154.68 -3855.72 30.48300 c/z -3855.72 -3855.72 30.48301 c/z -350.52 -4556.76 30.48302 c/z -1051.56 -4556.76 30.48303 c/z -1752.60 -4556.76 30.48304 c/z -2453.64 -4556.76 30.48305 c/z -3154.68 -4556.76 30.48306 c/z -350.52 -5257.80 30.48307 c/z -1051.56 -5257.80 30.48308 c/z -1752.60 -5257.80 30.48c VOLUME DETECTORS 30 CM ABOVE ROOF401 rcc 0 0 1371.12 0 0 1 1447402 rcc 0 0 1371.12 0 0 1 2894403 rcc 0 0 1371.12 0 0 1 4341404 rcc 0 0 1371.12 0 0 1 5786405 rcc 5877.56 0 1391.12 0 0 100 30 $Top of Stair Towerc VOLUME DETECTORS RADIALLY AROUND SDU @ 4' ABOVE GROUND406 s 5788.18 0 121.92 5407 s 6062.98 0 121.92 15408 s 6367.78 0 121.92 15409 s 6672.58 0 121.92 15410 s 6977.38 0 121.92 15411 s 7282.18 0 121.92 15412 s 7586.98 0 121.92 15413 s 7891.78 0 121.92 15414 s 8196.58 0 121.92 15415 s 8501.38 0 121.92 15416 s 8806.18 0 121.92 15417 s 9110.98 0 121.92 15418 s 9415.78 0 121.92 15419 s 9720.58 0 121.92 15420 s 10025.38 0 121.92 15421 s 10330.18 0 121.92 15422 s 10634.98 0 121.92 15

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.39 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

423 s 10939.78 0 121.92 15424 s 11244.58 0 121.92 15c VOLUME DETECTORS RADIALLY AROUND SDU @ 10' ABOVE GROUND425 s 5788.18 0 304.80 5426 s 6062.98 0 304.80 15427 s 6367.78 0 304.80 15428 s 6672.58 0 304.80 15429 s 6977.38 0 304.80 15430 s 7282.18 0 304.80 15431 s 7586.98 0 304.80 15432 s 7891.78 0 304.80 15433 s 8196.58 0 304.80 15434 s 8501.38 0 304.80 15435 s 8806.18 0 304.80 15436 s 9110.98 0 304.80 15437 s 9415.78 0 304.80 15438 s 9720.58 0 304.80 15439 s 10025.38 0 304.80 15440 s 10330.18 0 304.80 15441 s 10634.98 0 304.80 15442 s 10939.78 0 304.80 15443 s 11244.58 0 304.80 15c VOLUME DETECTORS RADIALLY AROUND SDU @ 20' ABOVE GROUND444 s 5788.18 0 609.60 5445 s 6062.98 0 609.60 15446 s 6367.78 0 609.60 15447 s 6672.58 0 609.60 15448 s 6977.38 0 609.60 15449 s 7282.18 0 609.60 15450 s 7586.98 0 609.60 15451 s 7891.78 0 609.60 15452 s 8196.58 0 609.60 15453 s 8501.38 0 609.60 15454 s 8806.18 0 609.60 15455 s 9110.98 0 609.60 15456 s 9415.78 0 609.60 15457 s 9720.58 0 609.60 15458 s 10025.38 0 609.60 15459 s 10330.18 0 609.60 15460 s 10634.98 0 609.60 15461 s 10939.78 0 609.60 15462 s 11244.58 0 609.60 15c VOLUME DETECTORS RADIALLY AROUND SDU @ 30' ABOVE GROUND463 s 5788.18 0 914.40 5464 s 6062.98 0 914.40 15465 s 6367.78 0 914.40 15466 s 6672.58 0 914.40 15467 s 6977.38 0 914.40 15468 s 7282.18 0 914.40 15469 s 7586.98 0 914.40 15470 s 7891.78 0 914.40 15471 s 8196.58 0 914.40 15472 s 8501.38 0 914.40 15473 s 8806.18 0 914.40 15474 s 9110.98 0 914.40 15475 s 9415.78 0 914.40 15476 s 9720.58 0 914.40 15477 s 10025.38 0 914.40 15478 s 10330.18 0 914.40 15479 s 10634.98 0 914.40 15480 s 10939.78 0 914.40 15481 s 11244.58 0 914.40 15c VOLUME DETECTORS RADIALLY AROUND SDU @ 40' ABOVE GROUND482 s 5788.18 0 1219.20 5483 s 6062.98 0 1219.20 15484 s 6367.78 0 1219.20 15485 s 6672.58 0 1219.20 15486 s 6977.38 0 1219.20 15

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.40 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

487 s 7282.18 0 1219.20 15488 s 7586.98 0 1219.20 15489 s 7891.78 0 1219.20 15490 s 8196.58 0 1219.20 15491 s 8501.38 0 1219.20 15492 s 8806.18 0 1219.20 15493 s 9110.98 0 1219.20 15494 s 9415.78 0 1219.20 15495 s 9720.58 0 1219.20 15496 s 10025.38 0 1219.20 15497 s 10330.18 0 1219.20 15498 s 10634.98 0 1219.20 15499 s 10939.78 0 1219.20 15500 s 11244.58 0 1219.20 15

c DATA CARDScmode pphys:p 100 0 0 0 0sdef erg d1 cel d2 rad fcel d3 ext fcel d6 pos fcel d9 axs 0 0 1cc Source Energy Groupingssi1 0.01 0.05 0.10 0.20 0.30 0.40 0.60 0.80 1.00 1.33 1.66 2.00 2.50 3.00cc Spectral Probabilities (Grout from 0.015 Ci/gal DSS)sp1 0.0000E+00 9.0320E-02 1.4097E-03 1.0268E-03 1.7656E-04 1.0253E-04 5.6600E-03 8.9757E-01 2.2738E-03 8.8279E-04 2.9602E-04 2.2415E-08 3.2337E-09 2.7631E-12csc2 Source Distributionsi2 L 2 3sp2 0.2963384468 0.7036615532csc3 Sources' Radiids3 S d4 d5csc4 Lower Source Radiussi4 5647.22 5729.77sp4 -21 1csc5 Upper Source Radiussi5 0 5731.13sp5 -21 1csc6 Sources' Extentsds6 S d7 d8csc7 Lower Source Extentsi7 0 1199.68sp7 0 1csc8 Upper Source Extentsi8 0 50sp8 0 1csc9 Sources' Positionsds9 S d10 d11csc10 Lower Source Positionsi10 L 0 0 0sp10 1

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.41 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

csc11 Upper Source Positionsi11 L 0 0 1199.68sp11 1cc Dose Conversion Factors (ICRP 74, Hp(10)) for photonscde0 0.01 0.015 0.02 0.03 0.04 0.05 0.06 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1 1.5 3 6 10 df0 2.4624E-05 3.0508E-04 3.8053E-04 2.9584E-04 2.3494E-04 2.0853E-04 1.9889E-04 2.1100E-04 2.4253E-04 3.4711E-04 4.5977E-04 6.8012E-04 8.8452E-04 1.0761E-03 1.2535E-03 1.5808E-03 1.8779E-03 2.5094E-03 3.9770E-03 6.3080E-03 9.2791E-03cc Multiplier = Origen output for highest result @ 0.1 yr decayc = (2.841E+08 p/s/Ci/gal) * (1,921,000) gal) = 5.45756E+14c = 5.45756E+14cfc4 Volume Detectors 30 cm Above Rooff4:p 401 402 403 404 405fm4 5.45756E+14fq4 f dcfc14 Volume Detectors Radially @ 4' Above Groundf14:p 406 407 408 409 410 411 412 413 414 415 416 417 418 419 420 421 422 423 424fm14 5.45756E+14fq14 f dcfc24 Volume Detectors Radially @ 10' Above Groundf24:p 425 426 427 428 429 430 431 432 433 434 435 436 437 438 439 440 441 442 443fm24 5.45756E+14fq24 f dcfc34 Volume Detectors Radially @ 20' Above Groundf34:p 444 445 446 447 448 449 450 451 452 453 454 455 456 457 458 459 460 461 462fm34 5.45756E+14fq34 f dcfc44 Volume Detectors Radially @ 30' Above Groundf44:p 463 464 465 466 467 468 469 470 471 472 473 474 475 476 477 478 479 480 481fm44 5.45756E+14fq44 f dcfc54 Volume Detectors Radially @ 40' Above Groundf54:p 482 483 484 485 486 487 488 489 490 491 492 493 494 495 496 497 498 499 500fm54 5.45756E+14fq54 f dcc Saltstone Grout (Density = 1.7007 g/cc) [Ref: S-CLC-Z-00041, Rev. 0]m1 1000 -0.053479 8000 -0.609656 12000 -0.008697 13000 -0.046681 14000 -0.035886 16000 -0.005398 20000 -0.001100 22000 -0.140544 26000 -0.098561cc Dry Air (Density = 0.001205 g/cc) [Ref: PNNL-15870, Rev. 1]m2 6000 -0.000124 7000 -0.755268 8000 -0.231781 18000 -0.012827cc Portland Concrete (Density = 2.3 g/cc) [Ref: PNNL-15870, Rev. 1]m3 1000 -0.010000 6000 -0.001000 8000 -0.529107 11000 -0.016000 12000 -0.002000 13000 -0.033872 14000 -0.337021 19000 -0.013000

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.42 of 63

Rev.0

Appendix G (continued) – Example MCNP Input File (S6015N) for SDU 6 Dose Rate Profile

20000 -0.044000 26000 -0.014000ccut:p j 0.1

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.43 of 63

Rev.0

Appendix H – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration

SDU6 PENETRATION ANALYSIS (0.015 Ci/gal) - 6' x 8' MANWAY + 1' HATCH COVERcc CELL CARDSc1 1 -1.7007 -1 101 206I 308 imp:p=1 $Up Source 1 (Grout)2 1 -1.7007 -2 101 206I 308 imp:p=3 $Up Source 2 (Grout)3 1 -1.7007 -3 101 206I 308 imp:p=10 $Up Source 3 (Grout)4 1 -1.7007 -4 101 206I 308 imp:p=30 $Up Source 4 (Grout)5 1 -1.7007 -5 101 206I 308 imp:p=90 $Up Source 5 (Grout)6 2 -0.001205 -6 101 206I 308 imp:p=240 $Vapor Space (Air)7 0 1 2 3 4 5 6 -7 imp:p=0 $Wall (Void)8 3 -2.3 -8 14 imp:p=290 $Roof 1 (Concrete)9 3 -2.3 -9 14 imp:p=1300 $Roof 2 (Concrete)10 3 -2.3 -10 14 imp:p=6330 $Roof 3 (Concrete)11 2 -0.001205 7 8 9 10 -13 21 22 imp:p=30900 $Atmosphere (Air)12 0 13 imp:p=0 $Universe (Void)13 2 -0.001205 -14 23 imp:p=1300 $Opening (Air)c CURB & HATCH COVER20 3 -2.3 20 -21 imp:p=6330 $Curb (Concrete)21 3 -2.3 -22:-23 imp:p=6330 $Hatch Cover (Concrete)c NW QUADRANT INTERIOR COLUMNS----------------------------------------------101 3 -2.3 -11 12 -101 imp:p=1102 3 -2.3 -11 12 -102 imp:p=1103 3 -2.3 -11 12 -103 imp:p=1104 3 -2.3 -11 12 -104 imp:p=1105 3 -2.3 -11 12 -105 imp:p=1106 3 -2.3 -11 12 -106 imp:p=1107 3 -2.3 -11 12 -107 imp:p=1108 3 -2.3 -11 12 -108 imp:p=1109 3 -2.3 -11 12 -109 imp:p=1110 3 -2.3 -11 12 -110 imp:p=1111 3 -2.3 -11 12 -111 imp:p=1112 3 -2.3 -11 12 -112 imp:p=1113 3 -2.3 -11 12 -113 imp:p=1114 3 -2.3 -11 12 -114 imp:p=1115 3 -2.3 -11 12 -115 imp:p=1116 3 -2.3 -11 12 -116 imp:p=1117 3 -2.3 -11 12 -117 imp:p=1118 3 -2.3 -11 12 -118 imp:p=1119 3 -2.3 -11 12 -119 imp:p=1120 3 -2.3 -11 12 -120 imp:p=1121 3 -2.3 -11 12 -121 imp:p=1122 3 -2.3 -11 12 -122 imp:p=1123 3 -2.3 -11 12 -123 imp:p=1124 3 -2.3 -11 12 -124 imp:p=1125 3 -2.3 -11 12 -125 imp:p=1126 3 -2.3 -11 12 -126 imp:p=1127 3 -2.3 -11 12 -127 imp:p=1128 3 -2.3 -11 12 -128 imp:p=1129 3 -2.3 -11 12 -129 imp:p=1130 3 -2.3 -11 12 -130 imp:p=1131 3 -2.3 -11 12 -131 imp:p=1132 3 -2.3 -11 12 -132 imp:p=1133 3 -2.3 -11 12 -133 imp:p=1134 3 -2.3 -11 12 -134 imp:p=1135 3 -2.3 -11 12 -135 imp:p=1136 3 -2.3 -11 12 -136 imp:p=1137 3 -2.3 -11 12 -137 imp:p=1138 3 -2.3 -11 12 -138 imp:p=1139 3 -2.3 -11 12 -139 imp:p=1140 3 -2.3 -11 12 -140 imp:p=1141 3 -2.3 -11 12 -141 imp:p=1142 3 -2.3 -11 12 -142 imp:p=1143 3 -2.3 -11 12 -143 imp:p=1144 3 -2.3 -11 12 -144 imp:p=1145 3 -2.3 -11 12 -145 imp:p=1146 3 -2.3 -11 12 -146 imp:p=1147 3 -2.3 -11 12 -147 imp:p=1

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.44 of 63

Rev.0

Appendix H (continued) – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration

148 3 -2.3 -11 12 -148 imp:p=1149 3 -2.3 -11 12 -149 imp:p=1150 3 -2.3 -11 12 -150 imp:p=1151 3 -2.3 -11 12 -151 imp:p=1152 3 -2.3 -11 12 -152 imp:p=1c NE QUADRANT INTERIOR COLUMNS----------------------------------------------153 3 -2.3 -11 12 -153 imp:p=1154 3 -2.3 -11 12 -154 imp:p=1155 3 -2.3 -11 12 -155 imp:p=1156 3 -2.3 -11 12 -156 imp:p=1157 3 -2.3 -11 12 -157 imp:p=1158 3 -2.3 -11 12 -158 imp:p=1159 3 -2.3 -11 12 -159 imp:p=1160 3 -2.3 -11 12 -160 imp:p=1161 3 -2.3 -11 12 -161 imp:p=1162 3 -2.3 -11 12 -162 imp:p=1163 3 -2.3 -11 12 -163 imp:p=1164 3 -2.3 -11 12 -164 imp:p=1165 3 -2.3 -11 12 -165 imp:p=1166 3 -2.3 -11 12 -166 imp:p=1167 3 -2.3 -11 12 -167 imp:p=1168 3 -2.3 -11 12 -168 imp:p=1169 3 -2.3 -11 12 -169 imp:p=1170 3 -2.3 -11 12 -170 imp:p=1171 3 -2.3 -11 12 -171 imp:p=1172 3 -2.3 -11 12 -172 imp:p=1173 3 -2.3 -11 12 -173 imp:p=1174 3 -2.3 -11 12 -174 imp:p=1175 3 -2.3 -11 12 -175 imp:p=1176 3 -2.3 -11 12 -176 imp:p=1177 3 -2.3 -11 12 -177 imp:p=1178 3 -2.3 -11 12 -178 imp:p=1179 3 -2.3 -11 12 -179 imp:p=1180 3 -2.3 -11 12 -180 imp:p=1181 3 -2.3 -11 12 -181 imp:p=1182 3 -2.3 -11 12 -182 imp:p=1183 3 -2.3 -11 12 -183 imp:p=1184 3 -2.3 -11 12 -184 imp:p=1185 3 -2.3 -11 12 -185 imp:p=1186 3 -2.3 -11 12 -186 imp:p=1187 3 -2.3 -11 12 -187 imp:p=1188 3 -2.3 -11 12 -188 imp:p=1189 3 -2.3 -11 12 -189 imp:p=1190 3 -2.3 -11 12 -190 imp:p=1191 3 -2.3 -11 12 -191 imp:p=1192 3 -2.3 -11 12 -192 imp:p=1193 3 -2.3 -11 12 -193 imp:p=1194 3 -2.3 -11 12 -194 imp:p=1195 3 -2.3 -11 12 -195 imp:p=1196 3 -2.3 -11 12 -196 imp:p=1197 3 -2.3 -11 12 -197 imp:p=1198 3 -2.3 -11 12 -198 imp:p=1199 3 -2.3 -11 12 -199 imp:p=1200 3 -2.3 -11 12 -200 imp:p=1201 3 -2.3 -11 12 -201 imp:p=1202 3 -2.3 -11 12 -202 imp:p=1203 3 -2.3 -11 12 -203 imp:p=1204 3 -2.3 -11 12 -204 imp:p=1c SE QUADRANT INTERIOR COLUMNS----------------------------------------------205 3 -2.3 -11 12 -205 imp:p=1206 3 -2.3 -11 12 -206 imp:p=1207 3 -2.3 -11 12 -207 imp:p=1208 3 -2.3 -11 12 -208 imp:p=1209 3 -2.3 -11 12 -209 imp:p=1210 3 -2.3 -11 12 -210 imp:p=1211 3 -2.3 -11 12 -211 imp:p=1212 3 -2.3 -11 12 -212 imp:p=1213 3 -2.3 -11 12 -213 imp:p=1

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.45 of 63

Rev.0

Appendix H (continued) – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration

214 3 -2.3 -11 12 -214 imp:p=1215 3 -2.3 -11 12 -215 imp:p=1216 3 -2.3 -11 12 -216 imp:p=1217 3 -2.3 -11 12 -217 imp:p=1218 3 -2.3 -11 12 -218 imp:p=1219 3 -2.3 -11 12 -219 imp:p=1220 3 -2.3 -11 12 -220 imp:p=1221 3 -2.3 -11 12 -221 imp:p=1222 3 -2.3 -11 12 -222 imp:p=1223 3 -2.3 -11 12 -223 imp:p=1224 3 -2.3 -11 12 -224 imp:p=1225 3 -2.3 -11 12 -225 imp:p=1226 3 -2.3 -11 12 -226 imp:p=1227 3 -2.3 -11 12 -227 imp:p=1228 3 -2.3 -11 12 -228 imp:p=1229 3 -2.3 -11 12 -229 imp:p=1230 3 -2.3 -11 12 -230 imp:p=1231 3 -2.3 -11 12 -231 imp:p=1232 3 -2.3 -11 12 -232 imp:p=1233 3 -2.3 -11 12 -233 imp:p=1234 3 -2.3 -11 12 -234 imp:p=1235 3 -2.3 -11 12 -235 imp:p=1236 3 -2.3 -11 12 -236 imp:p=1237 3 -2.3 -11 12 -237 imp:p=1238 3 -2.3 -11 12 -238 imp:p=1239 3 -2.3 -11 12 -239 imp:p=1240 3 -2.3 -11 12 -240 imp:p=1241 3 -2.3 -11 12 -241 imp:p=1242 3 -2.3 -11 12 -242 imp:p=1243 3 -2.3 -11 12 -243 imp:p=1244 3 -2.3 -11 12 -244 imp:p=1245 3 -2.3 -11 12 -245 imp:p=1246 3 -2.3 -11 12 -246 imp:p=1247 3 -2.3 -11 12 -247 imp:p=1248 3 -2.3 -11 12 -248 imp:p=1249 3 -2.3 -11 12 -249 imp:p=1250 3 -2.3 -11 12 -250 imp:p=1251 3 -2.3 -11 12 -251 imp:p=1252 3 -2.3 -11 12 -252 imp:p=1253 3 -2.3 -11 12 -253 imp:p=1254 3 -2.3 -11 12 -254 imp:p=1255 3 -2.3 -11 12 -255 imp:p=1256 3 -2.3 -11 12 -256 imp:p=1c SW QUADRANT INTERIOR COLUMNS----------------------------------------------257 3 -2.3 -11 12 -257 imp:p=1258 3 -2.3 -11 12 -258 imp:p=1259 3 -2.3 -11 12 -259 imp:p=1260 3 -2.3 -11 12 -260 imp:p=1261 3 -2.3 -11 12 -261 imp:p=1262 3 -2.3 -11 12 -262 imp:p=1263 3 -2.3 -11 12 -263 imp:p=1264 3 -2.3 -11 12 -264 imp:p=1265 3 -2.3 -11 12 -265 imp:p=1266 3 -2.3 -11 12 -266 imp:p=1267 3 -2.3 -11 12 -267 imp:p=1268 3 -2.3 -11 12 -268 imp:p=1269 3 -2.3 -11 12 -269 imp:p=1270 3 -2.3 -11 12 -270 imp:p=1271 3 -2.3 -11 12 -271 imp:p=1272 3 -2.3 -11 12 -272 imp:p=1273 3 -2.3 -11 12 -273 imp:p=1274 3 -2.3 -11 12 -274 imp:p=1275 3 -2.3 -11 12 -275 imp:p=1276 3 -2.3 -11 12 -276 imp:p=1277 3 -2.3 -11 12 -277 imp:p=1278 3 -2.3 -11 12 -278 imp:p=1279 3 -2.3 -11 12 -279 imp:p=1280 3 -2.3 -11 12 -280 imp:p=1

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.46 of 63

Rev.0

Appendix H (continued) – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration

281 3 -2.3 -11 12 -281 imp:p=1282 3 -2.3 -11 12 -282 imp:p=1283 3 -2.3 -11 12 -283 imp:p=1284 3 -2.3 -11 12 -284 imp:p=1285 3 -2.3 -11 12 -285 imp:p=1286 3 -2.3 -11 12 -286 imp:p=1287 3 -2.3 -11 12 -287 imp:p=1288 3 -2.3 -11 12 -288 imp:p=1289 3 -2.3 -11 12 -289 imp:p=1290 3 -2.3 -11 12 -290 imp:p=1291 3 -2.3 -11 12 -291 imp:p=1292 3 -2.3 -11 12 -292 imp:p=1293 3 -2.3 -11 12 -293 imp:p=1294 3 -2.3 -11 12 -294 imp:p=1295 3 -2.3 -11 12 -295 imp:p=1296 3 -2.3 -11 12 -296 imp:p=1297 3 -2.3 -11 12 -297 imp:p=1298 3 -2.3 -11 12 -298 imp:p=1299 3 -2.3 -11 12 -299 imp:p=1300 3 -2.3 -11 12 -300 imp:p=1301 3 -2.3 -11 12 -301 imp:p=1302 3 -2.3 -11 12 -302 imp:p=1303 3 -2.3 -11 12 -303 imp:p=1304 3 -2.3 -11 12 -304 imp:p=1305 3 -2.3 -11 12 -305 imp:p=1306 3 -2.3 -11 12 -306 imp:p=1307 3 -2.3 -11 12 -307 imp:p=1308 3 -2.3 -11 12 -308 imp:p=1

c SURFACE CARDSc1 trc 0 0 0 0 0 10.00 5729.77 5730.04 $Upper Source 12 trc 0 0 10 0 0 10.00 5730.04 5730.31 $Upper Source 23 trc 0 0 20 0 0 10.00 5730.31 5730.59 $Upper Source 34 trc 0 0 30 0 0 10.00 5730.59 5730.86 $Upper Source 45 trc 0 0 40 0 0 10.00 5730.86 5731.13 $Upper Source 56 trc 0 0 50 0 0 60.96 5731.13 5732.78 $Vapor Space7 rcc 0 0 0.00 0 0 110.96 5758.18 $Wall Exterior8 rcc 0 0 110.96 0 0 10.16 5758.18 $Roof 19 rcc 0 0 121.12 0 0 10.16 5758.18 $Roof 210 rcc 0 0 131.28 0 0 10.16 5758.18 $Roof 311 pz 110.96 $Column Top12 pz 0 $Column Bottom13 rcc 0 0 0 0 0 3200 5758.18 $Problem Boundary14 rpp -91.44 91.44 -121.92 121.92 110.96 171.92 $6' x 8' Rect. Openingc CURB & HATCH COVER20 rpp -91.44 91.44 -121.92 121.92 141.44 171.92 $Inner Curb21 rpp -121.92 121.92 -152.40 152.40 141.44 171.92 $Outer Curb22 rpp -121.92 121.92 -152.40 152.40 171.92 197.32 $Upper Hatch Cover23 arb -86.36 116.84 166.84 86.36 116.84 166.84 86.36 -116.84 166.84 -86.36 -116.84 166.84 -91.44 121.92 171.92 91.44 121.92 171.92 91.44 -121.92 171.92 -91.44 -121.92 171.92 1234 5678 1256 2367 3478 1458 $Lower Hatch Coverc NW QUADRANT INTERIOR COLUMNS----------------------------------------------101 c/z -350.52 350.52 30.48102 c/z -1051.56 350.52 30.48103 c/z -1752.60 350.52 30.48104 c/z -2453.64 350.52 30.48105 c/z -3154.68 350.52 30.48106 c/z -3855.72 350.52 30.48107 c/z -4556.76 350.52 30.48108 c/z -5257.80 350.52 30.48109 c/z -350.52 1051.56 30.48110 c/z -1051.56 1051.56 30.48111 c/z -1752.60 1051.56 30.48112 c/z -2453.64 1051.56 30.48113 c/z -3154.68 1051.56 30.48114 c/z -3855.72 1051.56 30.48

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.47 of 63

Rev.0

Appendix H (continued) – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration

115 c/z -4556.76 1051.56 30.48116 c/z -5257.80 1051.56 30.48117 c/z -350.52 1752.60 30.48118 c/z -1051.56 1752.60 30.48119 c/z -1752.60 1752.60 30.48120 c/z -2453.64 1752.60 30.48121 c/z -3154.68 1752.60 30.48122 c/z -3855.72 1752.60 30.48123 c/z -4556.76 1752.60 30.48124 c/z -5257.80 1752.60 30.48125 c/z -350.52 2453.64 30.48126 c/z -1051.56 2453.64 30.48127 c/z -1752.60 2453.64 30.48128 c/z -2453.64 2453.64 30.48129 c/z -3154.68 2453.64 30.48130 c/z -3855.72 2453.64 30.48131 c/z -4556.76 2453.64 30.48132 c/z -350.52 3154.68 30.48133 c/z -1051.56 3154.68 30.48134 c/z -1752.60 3154.68 30.48135 c/z -2453.64 3154.68 30.48136 c/z -3154.68 3154.68 30.48137 c/z -3855.72 3154.68 30.48138 c/z -4556.76 3154.68 30.48139 c/z -350.52 3855.72 30.48140 c/z -1051.56 3855.72 30.48141 c/z -1752.60 3855.72 30.48142 c/z -2453.64 3855.72 30.48143 c/z -3154.68 3855.72 30.48144 c/z -3855.72 3855.72 30.48145 c/z -350.52 4556.76 30.48146 c/z -1051.56 4556.76 30.48147 c/z -1752.60 4556.76 30.48148 c/z -2453.64 4556.76 30.48149 c/z -3154.68 4556.76 30.48150 c/z -350.52 5257.80 30.48151 c/z -1051.56 5257.80 30.48152 c/z -1752.60 5257.80 30.48c NE QUADRANT INTERIOR COLUMNS----------------------------------------------153 c/z 350.52 350.52 30.48154 c/z 1051.56 350.52 30.48155 c/z 1752.60 350.52 30.48156 c/z 2453.64 350.52 30.48157 c/z 3154.68 350.52 30.48158 c/z 3855.72 350.52 30.48159 c/z 4556.76 350.52 30.48160 c/z 5257.80 350.52 30.48161 c/z 350.52 1051.56 30.48162 c/z 1051.56 1051.56 30.48163 c/z 1752.60 1051.56 30.48164 c/z 2453.64 1051.56 30.48165 c/z 3154.68 1051.56 30.48166 c/z 3855.72 1051.56 30.48167 c/z 4556.76 1051.56 30.48168 c/z 5257.80 1051.56 30.48169 c/z 350.52 1752.60 30.48170 c/z 1051.56 1752.60 30.48171 c/z 1752.60 1752.60 30.48172 c/z 2453.64 1752.60 30.48173 c/z 3154.68 1752.60 30.48174 c/z 3855.72 1752.60 30.48175 c/z 4556.76 1752.60 30.48176 c/z 5257.80 1752.60 30.48177 c/z 350.52 2453.64 30.48178 c/z 1051.56 2453.64 30.48179 c/z 1752.60 2453.64 30.48180 c/z 2453.64 2453.64 30.48181 c/z 3154.68 2453.64 30.48

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.48 of 63

Rev.0

Appendix H (continued) – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration

182 c/z 3855.72 2453.64 30.48183 c/z 4556.76 2453.64 30.48184 c/z 350.52 3154.68 30.48185 c/z 1051.56 3154.68 30.48186 c/z 1752.60 3154.68 30.48187 c/z 2453.64 3154.68 30.48188 c/z 3154.68 3154.68 30.48189 c/z 3855.72 3154.68 30.48190 c/z 4556.76 3154.68 30.48191 c/z 350.52 3855.72 30.48192 c/z 1051.56 3855.72 30.48193 c/z 1752.60 3855.72 30.48194 c/z 2453.64 3855.72 30.48195 c/z 3154.68 3855.72 30.48196 c/z 3855.72 3855.72 30.48197 c/z 350.52 4556.76 30.48198 c/z 1051.56 4556.76 30.48199 c/z 1752.60 4556.76 30.48200 c/z 2453.64 4556.76 30.48201 c/z 3154.68 4556.76 30.48202 c/z 350.52 5257.80 30.48203 c/z 1051.56 5257.80 30.48204 c/z 1752.60 5257.80 30.48c SE QUADRANT INTERIOR COLUMNS----------------------------------------------205 c/z 350.52 -350.52 30.48206 c/z 1051.56 -350.52 30.48207 c/z 1752.60 -350.52 30.48208 c/z 2453.64 -350.52 30.48209 c/z 3154.68 -350.52 30.48210 c/z 3855.72 -350.52 30.48211 c/z 4556.76 -350.52 30.48212 c/z 5257.80 -350.52 30.48213 c/z 350.52 -1051.56 30.48214 c/z 1051.56 -1051.56 30.48215 c/z 1752.60 -1051.56 30.48216 c/z 2453.64 -1051.56 30.48217 c/z 3154.68 -1051.56 30.48218 c/z 3855.72 -1051.56 30.48219 c/z 4556.76 -1051.56 30.48220 c/z 5257.80 -1051.56 30.48221 c/z 350.52 -1752.60 30.48222 c/z 1051.56 -1752.60 30.48223 c/z 1752.60 -1752.60 30.48224 c/z 2453.64 -1752.60 30.48225 c/z 3154.68 -1752.60 30.48226 c/z 3855.72 -1752.60 30.48227 c/z 4556.76 -1752.60 30.48228 c/z 5257.80 -1752.60 30.48229 c/z 350.52 -2453.64 30.48230 c/z 1051.56 -2453.64 30.48231 c/z 1752.60 -2453.64 30.48232 c/z 2453.64 -2453.64 30.48233 c/z 3154.68 -2453.64 30.48234 c/z 3855.72 -2453.64 30.48235 c/z 4556.76 -2453.64 30.48236 c/z 350.52 -3154.68 30.48237 c/z 1051.56 -3154.68 30.48238 c/z 1752.60 -3154.68 30.48239 c/z 2453.64 -3154.68 30.48240 c/z 3154.68 -3154.68 30.48241 c/z 3855.72 -3154.68 30.48242 c/z 4556.76 -3154.68 30.48243 c/z 350.52 -3855.72 30.48244 c/z 1051.56 -3855.72 30.48245 c/z 1752.60 -3855.72 30.48246 c/z 2453.64 -3855.72 30.48247 c/z 3154.68 -3855.72 30.48248 c/z 3855.72 -3855.72 30.48

Page 49: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.49 of 63

Rev.0

Appendix H (continued) – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration

249 c/z 350.52 -4556.76 30.48250 c/z 1051.56 -4556.76 30.48251 c/z 1752.60 -4556.76 30.48252 c/z 2453.64 -4556.76 30.48253 c/z 3154.68 -4556.76 30.48254 c/z 350.52 -5257.80 30.48255 c/z 1051.56 -5257.80 30.48256 c/z 1752.60 -5257.80 30.48c SW QUADRANT INTERIOR COLUMNS----------------------------------------------257 c/z -350.52 -350.52 30.48258 c/z -1051.56 -350.52 30.48259 c/z -1752.60 -350.52 30.48260 c/z -2453.64 -350.52 30.48261 c/z -3154.68 -350.52 30.48262 c/z -3855.72 -350.52 30.48263 c/z -4556.76 -350.52 30.48264 c/z -5257.80 -350.52 30.48265 c/z -350.52 -1051.56 30.48266 c/z -1051.56 -1051.56 30.48267 c/z -1752.60 -1051.56 30.48268 c/z -2453.64 -1051.56 30.48269 c/z -3154.68 -1051.56 30.48270 c/z -3855.72 -1051.56 30.48271 c/z -4556.76 -1051.56 30.48272 c/z -5257.80 -1051.56 30.48273 c/z -350.52 -1752.60 30.48274 c/z -1051.56 -1752.60 30.48275 c/z -1752.60 -1752.60 30.48276 c/z -2453.64 -1752.60 30.48277 c/z -3154.68 -1752.60 30.48278 c/z -3855.72 -1752.60 30.48279 c/z -4556.76 -1752.60 30.48280 c/z -5257.80 -1752.60 30.48281 c/z -350.52 -2453.64 30.48282 c/z -1051.56 -2453.64 30.48283 c/z -1752.60 -2453.64 30.48284 c/z -2453.64 -2453.64 30.48285 c/z -3154.68 -2453.64 30.48286 c/z -3855.72 -2453.64 30.48287 c/z -4556.76 -2453.64 30.48288 c/z -350.52 -3154.68 30.48289 c/z -1051.56 -3154.68 30.48290 c/z -1752.60 -3154.68 30.48291 c/z -2453.64 -3154.68 30.48292 c/z -3154.68 -3154.68 30.48293 c/z -3855.72 -3154.68 30.48294 c/z -4556.76 -3154.68 30.48295 c/z -350.52 -3855.72 30.48296 c/z -1051.56 -3855.72 30.48297 c/z -1752.60 -3855.72 30.48298 c/z -2453.64 -3855.72 30.48299 c/z -3154.68 -3855.72 30.48300 c/z -3855.72 -3855.72 30.48301 c/z -350.52 -4556.76 30.48302 c/z -1051.56 -4556.76 30.48303 c/z -1752.60 -4556.76 30.48304 c/z -2453.64 -4556.76 30.48305 c/z -3154.68 -4556.76 30.48306 c/z -350.52 -5257.80 30.48307 c/z -1051.56 -5257.80 30.48308 c/z -1752.60 -5257.80 30.48

c DATA CARDScmode pphys:p 100 0 0 0 0csdef erg d1

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.50 of 63

Rev.0

Appendix H (continued) – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration

cel d2 rad d3 ext d4 pos fcel d5 axs 0 0 1cc Source Energy Groupingssi1 0.01 0.05 0.10 0.20 0.30 0.40 0.60 0.80 1.00 1.33 1.66 2.00 2.50 3.00cc Spectral Probabilities (Grout from 0.015 Ci/gal DSS)sp1 0.0000E+00 9.0320E-02 1.4097E-03 1.0268E-03 1.7656E-04 1.0253E-04 5.6600E-03 8.9757E-01 2.2738E-03 8.8279E-04 2.9602E-04 2.2415E-08 3.2337E-09 2.7631E-12csc2 Source Distributionsi2 L 1 2 3 4 5sp2 0.19996173 0.19998069 0.20000000 0.20001931 0.20003827csc3 Upper Sources' Radiisi3 0 5731.13sp3 -21 1csc4 Upper Sources' Extentssi4 0 10sp4 0 1csc5 Sources' Positionsds5 S d6 d7 d8 d9 d10csc6 Upper Source 1 Positionsi6 L 0 0 0sp6 1csc7 Upper Source 2 Positionsi7 L 0 0 10sp7 1csc8 Upper Source 3 Positionsi8 L 0 0 20sp8 1csc9 Upper Source 4 Positionsi9 L 0 0 30sp9 1csc10 Upper Source 5 Positionsi10 L 0 0 40sp10 1cc Dose Conversion Factors (ICRP 74, Hp(10)) for photonscde0 0.01 0.015 0.02 0.03 0.04 0.05 0.06 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1 1.5 3 6 10 df0 2.4624E-05 3.0508E-04 3.8053E-04 2.9584E-04 2.3494E-04 2.0853E-04 1.9889E-04 2.1100E-04 2.4253E-04 3.4711E-04 4.5977E-04 6.8012E-04 8.8452E-04 1.0761E-03 1.2535E-03 1.5808E-03 1.8779E-03 2.5094E-03 3.9770E-03 6.3080E-03 9.2791E-03cc Multiplier = Origen output for highest result @ 0.1 yr decayc = (2.841E+08 p/s/Ci/gal) * (1,354,631) gal) = 3.849E+14c

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.51 of 63

Rev.0

Appendix H (continued) – Example MCNP Input File (S63AHC) for SDU 6 Rooftop Penetration

fc5 Point Detectors Above Hatch Cover & Inside Above Grout Pourf5:p 0.00 0.00 227.32 5 91.44 0.00 227.32 5 0.00 -121.92 227.32 5 -91.44 0.00 227.32 5 0.00 121.92 227.32 5 0.00 0.00 80.00 5fm5 3.849E+14fq5 f dcc Saltstone Grout (Density = 1.7007 g/cc) [Ref: S-CLC-Z-00041, Rev. 0]m1 1000 -0.053479 8000 -0.609656 12000 -0.008697 13000 -0.046681 14000 -0.035886 16000 -0.005398 20000 -0.001100 22000 -0.140544 26000 -0.098561cc Dry Air (Density = 0.001205 g/cc) [Ref: PNNL-15870, Rev. 1]m2 6000 -0.000124 7000 -0.755268 8000 -0.231781 18000 -0.012827cc Portland Concrete (Density = 2.3 g/cc) [Ref: PNNL-15870, Rev. 1]m3 1000 -0.010000 6000 -0.001000 8000 -0.529107 11000 -0.016000 12000 -0.002000 13000 -0.033872 14000 -0.337021 19000 -0.013000 20000 -0.044000 26000 -0.014000cc Carbon Steel (Density = 7.82 g/cc) [Ref: PNNL-15870, Rev. 1]m4 6000 -0.005000 26000 -0.995000cctme 5000cut:p j 0.1

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OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.52 of 63

Rev.0

Appendix I – Example MCNP Input File (GL015) for SDU 6 Transfer Line

Unshielded 100' @ 3" Diam. Grout Line (Grout from 0.015 Ci/gal DSS)c1 1 -1.7007 -1 imp:p=1 $Grout Source2 2 -7.82 1 -2 imp:p=2 $Grout Line Wall3 3 -0.001205 2 -3 imp:p=4 $Atmosphere4 0 3 imp:p=0 $Universe

1 rcc -1523.45 0 0 3046.90 0 0 3.90 $Source 2 rcc -1524.00 0 0 3048.00 0 0 4.45 $100' @ 3" Sch 40 Steel (t = 0.55 cm)3 so 3100 $Problem Boundary

mode pphys:p 20 0 0 0 0sdef cel 1 erg d1 rad d2 ext d3 pos -1523.45 0 0 axs 1 0 0c c Source Energy Groupingssi1 0.01 0.05 0.10 0.20 0.30 0.40 0.60 0.80 1.00 1.33 1.66 2.00 2.50 3.00cc Spectral Probabilities (Grout from 0.015 Ci/gal DSS)sp1 0.0000E+00 9.0320E-02 1.4097E-03 1.0268E-03 1.7656E-04 1.0253E-04 5.6600E-03 8.9757E-01 2.2738E-03 8.8279E-04 2.9602E-04 2.2415E-08 3.2337E-09 2.7631E-12c sc2 Source Radiussi2 0 3.90sp2 -21 1csc3 Source Extentsi3 0 3046.90sp3 0 1 cc Dose Conversion Factors (ICRP 74, Hp(10)) for photonsCde0 0.01 0.015 0.02 0.03 0.04 0.05 0.06 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1 1.5 3 6 10 df0 2.4624E-05 3.0508E-04 3.8053E-04 2.9584E-04 2.3494E-04 2.0853E-04 1.9889E-04 2.1100E-04 2.4253E-04 3.4711E-04 4.5977E-04 6.8012E-04 8.8452E-04 1.0761E-03 1.2535E-03 1.5808E-03 1.8779E-03 2.5094E-03 3.9770E-03 6.3080E-03 9.2791E-03cc Multiplierc = (2.841E+08 p/s/Ci/gal) * (38.4613 gals) = 1.093E+10cfc5 Ring detectors at midpoint (50') of grout line (mrem/hr)f5x:p 0 9.45 1 $5 cm 0 34.45 5 $30 cm 0 65.41 5 $2' 0 95.89 5 $3' 0 126.37 5 $4' 0 156.85 5 $5' 0 187.33 5 $6' 0 217.81 5 $7' 0 248.29 5 $8' 0 278.77 5 $9' 0 309.25 5 $10'

Page 53: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.53 of 63

Rev.0

Appendix I (continued) – Example MCNP Input File (GL015) for SDU 6 Transfer Line

0 339.73 5 $11' 0 370.21 5 $12' 0 400.69 5 $13' 0 431.17 5 $14' 0 461.65 5 $15' 0 492.13 5 $16' 0 522.61 5 $17' 0 553.09 5 $18' 0 583.57 5 $19' 0 614.05 5 $20' 0 644.53 5 $21' 0 675.01 5 $22' 0 705.49 5 $23' 0 735.97 5 $24' 0 766.45 5 $25' 0 796.93 5 $26' 0 827.41 5 $27' 0 857.89 5 $28' 0 888.37 5 $29' 0 918.85 5 $30' 0 949.33 5 $31' 0 979.81 5 $32' 0 1010.29 5 $33' 0 1040.77 5 $34' 0 1071.25 5 $35' 0 1101.73 5 $36' 0 1132.21 5 $37' 0 1162.69 5 $38' 0 1193.17 5 $39' 0 1223.65 5 $40' 0 1254.13 5 $41' 0 1284.61 5 $42' 0 1315.09 5 $43' 0 1345.57 5 $44' 0 1376.05 5 $45' 0 1406.53 5 $46' 0 1437.01 5 $47' 0 1467.49 5 $48' 0 1497.97 5 $49' 0 1528.45 5 $50' 0 1558.93 5 $51' 0 1589.41 5 $52' 0 1619.89 5 $53' 0 1650.37 5 $54' 0 1680.85 5 $55' 0 1711.33 5 $56' 0 1741.81 5 $57' 0 1772.29 5 $58' 0 1802.77 5 $59' 0 1833.25 5 $60' 0 1863.73 5 $61' 0 1894.21 5 $62' 0 1924.69 5 $63' 0 1955.17 5 $64' 0 1985.65 5 $65' 0 2016.13 5 $66' 0 2046.61 5 $67' 0 2077.09 5 $68' 0 2107.57 5 $69' 0 2138.05 5 $70' 0 2168.53 5 $71' 0 2199.01 5 $72' 0 2229.49 5 $73' 0 2259.97 5 $74' 0 2290.45 5 $75'

Page 54: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.54 of 63

Rev.0

Appendix I (continued) – Example MCNP Input File (GL015) for SDU 6 Transfer Line

0 2320.93 5 $76' 0 2351.41 5 $77' 0 2381.89 5 $78' 0 2412.37 5 $79' 0 2442.85 5 $80' 0 2473.33 5 $81' 0 2503.81 5 $82' 0 2534.29 5 $83' 0 2564.77 5 $84' 0 2595.25 5 $85' 0 2625.73 5 $86' 0 2656.21 5 $87' 0 2686.69 5 $88' 0 2717.17 5 $89' 0 2747.65 5 $90' 0 2778.13 5 $91' 0 2808.61 5 $92' 0 2839.09 5 $93' 0 2869.57 5 $94' 0 2900.05 5 $95' 0 2930.53 5 $96' 0 2961.01 5 $97' 0 2991.49 5 $98' 0 3021.97 5 $99'fm5 1.093E+10fq5 f dcc Saltstone Grout (Density = 1.7007 g/cc) [Ref: S-CLC-Z-00041, Rev. 0]m1 1000 -0.053479 8000 -0.609656 12000 -0.008697 13000 -0.046681 14000 -0.035886 16000 -0.005398 20000 -0.001100 22000 -0.140544 26000 -0.098561cc Carbon Steel (Density = 7.82 g/cc) [Ref: PNNL-15870, Rev. 1]m2 6000 -0.005000 26000 -0.995000cc Dry Air (Density = 0.001205 g/cc) [Ref: PNNL-15870, Rev. 1]m3 6000 -0.000124 7000 -0.755268 8000 -0.231781 18000 -0.012827cctme 200cut:p j 0.1

Page 55: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.55 of 63

Rev.0

Appendix J – SDU 6 Dose Rate Profile (mrem/hr) for 0.0002 Ci/gal Grout

Above Radial Distance Away from SDU6 Perimeter

Grade 30 cm 10' 20' 30' 40' 50' 60' 70' 80' 90' 100' 110' 120' 130' 140' 150' 160' 170' 180'

@ 40' 0.09 0.04 0.02 0.02 0.01 0.01 0.009 0.008 0.007 0.006 0.005 0.004 0.004 0.003 0.004 0.003 0.002 0.002 0.002

@ 30' 0.03 0.03 0.02 0.02 0.01 0.01 0.008 0.007 0.006 0.005 0.005 0.004 0.004 0.003 0.003 0.003 0.002 0.002 0.002

@ 20' 0.01 0.01 0.01 0.01 0.01 0.009 0.007 0.007 0.006 0.005 0.004 0.004 0.003 0.003 0.003 0.003 0.002 0.002 0.002

@ 10' 0.003 0.005 0.007 0.007 0.008 0.007 0.006 0.006 0.005 0.004 0.004 0.004 0.003 0.003 0.003 0.002 0.002 0.002 0.002

@ 4' 0.002 0.003 0.004 0.005 0.006 0.005 0.005 0.005 0.004 0.004 0.004 0.003 0.003 0.003 0.002 0.002 0.002 0.002 0.002

Locationmrem/hr

@ 30 cm

Rooftop (Radius = 0 '- 47.5') 0.08

Rooftop (Radius = '47.5' - 95') 0.08

Rooftop (Radius = 95' - 142.5') 0.08

Rooftop (Radius = 142.5' - 190') 0.07

Stair Tower 0.01

Interior Above Grout Pour 14

RBA RA HRA VHRA

Page 56: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.56 of 63

Rev.0

Appendix K – SDU 6 Dose Rate Profile (mrem/hr) for 0.006 Ci/gal Grout

Above Radial Distance Away from SDU6 Perimeter

Grade 30 cm 10' 20' 30' 40' 50' 60' 70' 80' 90' 100' 110' 120' 130' 140' 150' 160' 170' 180'

@ 40' 2.0 0.8 0.5 0.4 0.3 0.2 0.2 0.2 0.1 0.1 0.1 0.09 0.08 0.07 0.07 0.06 0.05 0.05 0.05

@ 30' 0.7 0.6 0.5 0.3 0.3 0.2 0.2 0.2 0.1 0.1 0.1 0.09 0.08 0.07 0.06 0.06 0.06 0.05 0.04

@ 20' 0.2 0.2 0.3 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.09 0.08 0.08 0.07 0.06 0.06 0.05 0.04 0.04

@ 10' 0.06 0.09 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.09 0.08 0.08 0.07 0.07 0.06 0.05 0.04 0.04 0.04

@ 4' 0.04 0.06 0.08 0.1 0.1 0.1 0.1 0.1 0.09 0.08 0.08 0.07 0.07 0.06 0.05 0.05 0.04 0.04 0.04

Locationmrem/hr

@ 30 cm

Rooftop (Radius = 0 '- 47.5') 1.7

Rooftop (Radius = '47.5' - 95') 1.7

Rooftop (Radius = 95' - 142.5') 1.7

Rooftop (Radius = 142.5' - 190') 1.5

Stair Tower 0.3

Interior Above Grout Pour 324

RBA RA HRA VHRA

Page 57: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.57 of 63

Rev.0

Appendix L – SDU 6 Dose Rate Profile (mrem/hr) for 0.015 Ci/gal Grout

Above Radial Distance Away from SDU6 Perimeter

Grade 30 cm 10' 20' 30' 40' 50' 60' 70' 80' 90' 100' 110' 120' 130' 140' 150' 160' 170' 180'

@ 40' 4.7 2.1 1.2 0.9 0.7 0.6 0.5 0.4 0.3 0.3 0.3 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.1

@ 30' 1.6 1.5 1.1 0.8 0.7 0.6 0.5 0.4 0.3 0.3 0.3 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.1

@ 20' 0.4 0.6 0.6 0.6 0.5 0.4 0.4 0.3 0.3 0.2 0.2 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.1

@ 10' 0.1 0.2 0.3 0.4 0.4 0.3 0.3 0.3 0.3 0.2 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.1 0.09

@ 4' 0.08 0.1 0.2 0.2 0.3 0.3 0.2 0.3 0.2 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.1 0.1 0.09

Above Radial Distance Away from SDU6 Perimeter

Grade 190’ 200’ 210’ 220’ 230’ 240’ 250’ 260’ 270’ 280’ 290’ 300’ 310’ 320’ 330’ 340’ 350’ 360’ 370’ 380’

@ 40' 0.1 0.09 0.08 0.08 0.08 0.06 0.06 0.05 0.05 0.05 0.05 0.04 0.04 0.04 0.03 0.03 0.03 0.03 0.03 0.03

@ 30' 0.09 0.08 0.08 0.08 0.07 0.07 0.06 0.05 0.05 0.05 0.04 0.04 0.04 0.04 0.03 0.03 0.03 0.02 0.03 0.02

@ 20' 0.09 0.09 0.08 0.08 0.07 0.07 0.06 0.06 0.06 0.05 0.05 0.04 0.04 0.03 0.04 0.03 0.03 0.03 0.03 0.02

@ 10' 0.10 0.09 0.07 0.08 0.06 0.06 0.05 0.06 0.04 0.04 0.04 0.04 0.03 0.03 0.03 0.03 0.03 0.02 0.02 0.02

@ 4' 0.08 0.08 0.07 0.07 0.06 0.06 0.05 0.05 0.04 0.04 0.04 0.04 0.04 0.03 0.03 0.03 0.02 0.03 0.02 0.02

Locationmrem/hr

@ 30 cm

Rooftop (Radius = 0 '- 47.5') 4.2

Rooftop (Radius = '47.5' - 95') 4.1

Rooftop (Radius = 95' - 142.5') 4.1

Rooftop (Radius = 142.5' - 190') 3.8

Stair Tower 0.8

Interior Above Grout Pour 807

RBA RA HRA VHRA

Page 58: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.58 of 63

Rev.0

Appendix M – SDU 6 Dose Rate Profile (mrem/hr) for 0.03 Ci/gal Grout

Above Radial Distance Away from SDU6 Perimeter

Grade 30 cm 10' 20' 30' 40' 50' 60' 70' 80' 90' 100' 110' 120' 130' 140' 150' 160' 170' 180'

@ 40' 9.7 4.1 2.5 1.8 1.5 1.2 0.9 0.8 0.7 0.6 0.5 0.5 0.4 0.4 0.3 0.3 0.3 0.3 0.2

@ 30' 3.3 3.0 2.3 1.7 1.4 1.1 1.0 0.8 0.6 0.6 0.5 0.4 0.4 0.4 0.3 0.3 0.3 0.2 0.2

@ 20' 0.8 1.2 1.3 1.2 1.1 0.9 0.8 0.7 0.6 0.5 0.5 0.4 0.4 0.3 0.3 0.3 0.2 0.2 0.2

@ 10' 0.3 0.5 0.7 0.7 0.7 0.7 0.6 0.6 0.5 0.5 0.4 0.4 0.4 0.3 0.3 0.3 0.2 0.2 0.2

@ 4' 0.2 0.3 0.4 0.5 0.6 0.6 0.5 0.5 0.4 0.4 0.4 0.4 0.3 0.3 0.3 0.2 0.2 0.2 0.2

Above Radial Distance Away from SDU6 Perimeter

Grade 190’ 200’ 210’ 220’ 230’ 240’ 250’ 260’ 270’ 280’ 290’ 300’ 310’ 320’ 330’ 340’ 350’ 360’ 370’ 380’

@ 40' 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.1 0.1 0.1 0.09 0.09 0.08 0.07 0.07 0.07 0.06 0.06 0.06 0.05

@ 30' 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.1 0.1 0.1 0.09 0.08 0.08 0.08 0.06 0.06 0.06 0.05 0.05 0.05

@ 20' 0.2 0.2 0.2 0.2 0.1 0.1 0.1 0.1 0.1 0.1 0.09 0.07 0.07 0.07 0.07 0.06 0.06 0.06 0.06 0.05

@ 10' 0.2 0.2 0.2 0.1 0.1 0.1 0.1 0.1 0.09 0.09 0.08 0.08 0.07 0.06 0.06 0.06 0.05 0.04 0.05 0.04

@ 4' 0.2 0.2 0.1 0.1 0.1 0.1 0.1 0.1 0.08 0.09 0.07 0.07 0.08 0.07 0.06 0.06 0.05 0.05 0.04 0.04

Locationmrem/hr

@ 30 cm

Rooftop (Radius = 0 '- 47.5') 8.4

Rooftop (Radius = '47.5' - 95') 8.3

Rooftop (Radius = 95' - 142.5') 8.3

Rooftop (Radius = 142.5' - 190') 7.7

Stair Tower 1.6

Interior Above Grout Pour 1620

RBA RA HRA VHRA

Page 59: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.59 of 63

Rev.0

Appendix N – Dose Rates Through SDU 6 Rooftop Penetrations

PENETRATION DESCRIPTION

DOSE RATES

(mrem/hr @ 30 cm)

@ 0.0002 @ 0.006 @ 0.015 @ 0.03

Ci/gal Ci/gal Ci/gal Ci/gal

SDU Rooftop - General Area 0.08 1.7 4.2 8.4

Access Hatch (6' x 8')

Open 6.4 153 389 778

+ 1/4" Steel Sidewalk Door 4.6 110 270 545

+ 1/2" Steel Sidewalk Door 3.3 78 189 383

+ 1" Steel Sidewalk Door 1.7 39 96 192

+ 2" Steel Sidewalk Door X 11 26 53

+ 3" Steel Sidewalk Door X 3.3 7.8 16

+ 4" Steel Sidewalk Door X 1.2 3.1 6.1

+ 1' Concrete Curb & Cover 0.07 1.4 3.6 6.9

Active Vent (14" Diam.)

Open 0.4 7 20 42

+ 1/4" Steel Cover 0.3 6.6 16 32

Camera Port (12" Diam.)

Open 0.2 4.1 11 20

+ 3.18 cm Steel Victaulic®

Cap0.1 3.5 8.7 19

+ 1" Steel Cover 0.2 3.4 9.0 19

+ 1.5" Steel Cover 0.2 3.2 8.5 17

Drainwater Port (36" Diam.)

Open 1.2 29 74 149

+ 1/4" Steel Cover 1.0 24 59 118

+ 1" Steel Cover 0.6 15 38 76

Grout Port (3" Diam.)

Open 0.09 1.7 4.2 9.7

+ 2.24 cm Steel Victaulic®

Cap0.09 1.8 3.9 8.7

Passive Vent (12" Diam.)

Open 0.3 6.2 18 34

+ 1/4" Steel Cover 0.2 5.4 14 27

T/C Port (8" Diam.)

Open 0.1 3.2 7.0 14

+ 3.02 cm Steel Victaulic®

Cap0.1 2.8 5.5 11

+ 1/2" Steel Cover 0.1 2.6 5.2 10

RBA RA HRA VHRA

Page 60: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.60 of 63

Rev.0

Appendix O – Dose Rates from SDU 6 Transfer Lines

Distance

@ 0.0002 Ci/gal @ 0.006 Ci/gal @ 0.015 Ci/gal @ 0.03 Ci/gal

Drainwater Grout Drainwater Grout Drainwater Grout Drainwater Grout

Line Line Line Line Line Line Line Line

(mrem/hr) (mrem/hr) (mrem/hr) (mrem/hr)

5 cm 1.2 1.0 30 23 74 57 149 115

30 cm 0.3 0.3 7.2 6 18 15 36 31

2' 0.2 0.1 3.7 3.2 9.2 8.1 19 16

3' 0.1 0.09 2.5 2.2 6.3 5.5 13 11

4' 0.08 0.07 1.9 1.7 4.7 4.2 9.5 8.4

5' 0.06 0.06 1.5 1.4 3.8 3.4 7.6 6.8

6' 0.05 0.05 1.3 1.1 3.2 2.8 6.4 5.7

7' 0.05 0.04 1.1 1.0 2.7 2.4 5.5 4.8

8' 0.04 0.04 1.0 0.9 2.4 2.1 4.8 4.3

9' 0.04 0.03 0.8 0.8 2.1 1.9 4.2 3.8

10' 0.03 0.03 0.8 0.7 1.9 1.7 3.8 3.4

11' 0.03 0.03 0.7 0.6 1.7 1.5 3.4 3.1

12' 0.03 0.02 0.6 0.6 1.6 1.4 3.1 2.8

13' 0.02 0.02 0.6 0.5 1.4 1.3 2.9 2.6

14' 0.02 0.02 0.5 0.5 1.3 1.2 2.7 2.4

15' 0.02 0.02 0.5 0.4 1.2 1.1 2.5 2.2

16' 0.02 0.02 0.5 0.4 1.1 1.0 2.3 2.1

17' 0.02 0.02 0.4 0.4 1.1 1.0 2.1 2.0

18' 0.02 0.02 0.4 0.4 1.0 0.9 2.0 1.8

19' 0.02 0.01 0.4 0.3 0.9 0.9 1.9 1.7

20' 0.01 0.01 0.4 0.3 0.9 0.8 1.8 1.6

21' 0.01 0.01 0.3 0.3 0.8 0.8 1.7 1.5

22' 0.01 0.01 0.3 0.3 0.8 0.7 1.6 1.5

23' 0.01 0.01 0.3 0.3 0.8 0.7 1.5 1.4

24' 0.01 0.01 0.3 0.3 0.7 0.7 1.4 1.3

25' 0.01 0.01 0.3 0.3 0.7 0.6 1.4 1.3

26' 0.01 0.01 0.3 0.2 0.6 0.6 1.3 1.2

27' 0.01 0.01 0.2 0.2 0.6 0.6 1.2 1.1

28' 0.01 0.009 0.2 0.2 0.6 0.5 1.2 1.1

29' 0.009 0.009 0.2 0.2 0.6 0.5 1.1 1.0

30' 0.009 0.008 0.2 0.2 0.5 0.5 1.1 1.0

31' 0.009 0.008 0.2 0.2 0.5 0.5 1.0 1.0

32' 0.008 0.008 0.2 0.2 0.5 0.5 1.0 0.9

33' 0.008 0.007 0.2 0.2 0.5 0.4 0.9 0.9

34' 0.008 0.007 0.2 0.2 0.4 0.4 0.9 0.8

35' 0.007 0.007 0.2 0.2 0.4 0.4 0.9 0.8

36' 0.007 0.007 0.2 0.2 0.4 0.4 0.8 0.8

37' 0.007 0.006 0.2 0.2 0.4 0.4 0.8 0.8

38' 0.006 0.006 0.2 0.1 0.4 0.4 0.8 0.7

39' 0.006 0.006 0.1 0.1 0.4 0.4 0.7 0.7

40' 0.006 0.006 0.1 0.1 0.4 0.3 0.7 0.7

41' 0.006 0.006 0.1 0.1 0.3 0.3 0.7 0.7

42' 0.006 0.005 0.1 0.1 0.3 0.3 0.7 0.6

43' 0.005 0.005 0.1 0.1 0.3 0.3 0.6 0.6

44' 0.005 0.005 0.1 0.1 0.3 0.3 0.6 0.6

45' 0.005 0.005 0.1 0.1 0.3 0.3 0.6 0.6

46' 0.005 0.005 0.1 0.1 0.3 0.3 0.6 0.6

47' 0.005 0.004 0.1 0.1 0.3 0.3 0.6 0.5

48' 0.005 0.004 0.1 0.1 0.3 0.3 0.5 0.5

49' 0.004 0.004 0.1 0.1 0.3 0.2 0.5 0.5

50' 0.004 0.004 0.1 0.1 0.3 0.2 0.5 0.5

RBA RA HRA

Page 61: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.61 of 63

Rev.0

Appendix O (continued) – Dose Rates from SDU 6 Transfer Lines

Distance

@ 0.0002 Ci/gal @ 0.006 Ci/gal @ 0.015 Ci/gal @ 0.03 Ci/gal

Drainwater Grout Drainwater Grout Drainwater Grout Drainwater Grout

Line Line Line Line Line Line Line Line

(mrem/hr) (mrem/hr) (mrem/hr) (mrem/hr)

51' 0.004 0.004 0.1 0.09 0.2 0.2 0.5 0.5

52' 0.004 0.004 0.09 0.09 0.2 0.2 0.5 0.5

53' 0.004 0.004 0.09 0.09 0.2 0.2 0.5 0.4

54' 0.004 0.004 0.09 0.09 0.2 0.2 0.4 0.4

55' 0.004 0.004 0.09 0.08 0.2 0.2 0.4 0.4

56' 0.004 0.003 0.08 0.08 0.2 0.2 0.4 0.4

57' 0.003 0.003 0.08 0.08 0.2 0.2 0.4 0.4

58' 0.003 0.003 0.08 0.08 0.2 0.2 0.4 0.4

59' 0.003 0.003 0.08 0.07 0.2 0.2 0.4 0.4

60' 0.003 0.003 0.07 0.07 0.2 0.2 0.4 0.4

61' 0.003 0.003 0.07 0.07 0.2 0.2 0.4 0.4

62' 0.003 0.003 0.07 0.07 0.2 0.2 0.4 0.3

63' 0.003 0.003 0.07 0.07 0.2 0.2 0.3 0.3

64' 0.003 0.003 0.07 0.07 0.2 0.2 0.3 0.3

65' 0.003 0.003 0.07 0.06 0.2 0.2 0.3 0.3

66' 0.003 0.003 0.06 0.06 0.2 0.2 0.3 0.3

67' 0.003 0.003 0.06 0.06 0.2 0.1 0.3 0.3

68' 0.003 0.002 0.06 0.06 0.1 0.1 0.3 0.3

69' 0.002 0.002 0.06 0.06 0.1 0.1 0.3 0.3

70' 0.002 0.002 0.06 0.06 0.1 0.1 0.3 0.3

71' 0.002 0.002 0.06 0.05 0.1 0.1 0.3 0.3

72' 0.002 0.002 0.05 0.05 0.1 0.1 0.3 0.3

73' 0.002 0.002 0.05 0.05 0.1 0.1 0.3 0.3

74' 0.002 0.002 0.05 0.05 0.1 0.1 0.3 0.3

75' 0.002 0.002 0.05 0.05 0.1 0.1 0.3 0.2

76' 0.002 0.002 0.05 0.05 0.1 0.1 0.2 0.2

77' 0.002 0.002 0.05 0.05 0.1 0.1 0.2 0.2

78' 0.002 0.002 0.05 0.05 0.1 0.1 0.2 0.2

79' 0.002 0.002 0.05 0.04 0.1 0.1 0.2 0.2

80' 0.002 0.002 0.04 0.04 0.1 0.1 0.2 0.2

81' 0.002 0.002 0.04 0.04 0.1 0.1 0.2 0.2

82' 0.002 0.002 0.04 0.04 0.1 0.1 0.2 0.2

83' 0.002 0.002 0.04 0.04 0.1 0.1 0.2 0.2

84' 0.002 0.002 0.04 0.04 0.1 0.1 0.2 0.2

85' 0.002 0.002 0.04 0.04 0.1 0.1 0.2 0.2

86' 0.002 0.002 0.04 0.04 0.1 0.09 0.2 0.2

87' 0.002 0.002 0.04 0.04 0.09 0.09 0.2 0.2

88' 0.002 0.002 0.04 0.04 0.09 0.09 0.2 0.2

89' 0.002 0.001 0.04 0.04 0.09 0.09 0.2 0.2

90' 0.001 0.001 0.04 0.03 0.09 0.09 0.2 0.2

91' 0.001 0.001 0.03 0.03 0.09 0.08 0.2 0.2

92' 0.001 0.001 0.03 0.03 0.08 0.08 0.2 0.2

93' 0.001 0.001 0.03 0.03 0.08 0.08 0.2 0.2

94' 0.001 0.001 0.03 0.03 0.08 0.08 0.2 0.2

95' 0.001 0.001 0.03 0.03 0.08 0.08 0.2 0.2

96' 0.001 0.001 0.03 0.03 0.08 0.08 0.2 0.2

97' 0.001 0.001 0.03 0.03 0.08 0.07 0.2 0.2

98' 0.001 0.001 0.03 0.03 0.07 0.07 0.1 0.1

99' 0.001 0.001 0.03 0.03 0.07 0.07 0.1 0.1

RBA RA HRA

Page 62: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.62 of 63

Rev.0

Appendix P – Estimated Dose Rates to Equipment Submersed in the SDU 6 Drainwell

N-CLC-H-00673, Rev. 0, Radiation Material Qualification Calculation Inside the Submersible Mixer Pump (SMP) and Submersible Transfer Pump (STP) for Tanks 1 Through 15, (12/19/06) estimates dose rates to pumps submersed in much higher activity waste than that planned for SDU6 (i.e., 0.015 Ci/gal Cs-137). However, by scaling these dose rates down based on the ratio between the radioactivity of the predominant radionuclides in the two waste streams (i.e., Tanks 1-15 versus SDU6), potential dose rates to a submersible wastewater pump in the SDU6 drainwell can be estimated (see table below).

Predominant Radionuclides

N-CLC-H-00673 SDU6

Ci/gal1 Rad/hr2, 3 Rad/Yr Ci/gal4 Rad/hr Rad/Yr

gamma Cs-137 1.98266E+01 8.26E+03 7.2E+07 0.015 6 5.5E+04

beta SrY-90 7.1258E+01 4.73E+04 4.1E+08 0.0851718 57 5.0E+05

alphaAm-241 2.74948E-01 8.49E+02 7.4E+06 0.0009464 3 2.6E+04

Pu-238 7.05636E-02 2.19E+02 1.9E+06 0.0009464 3 2.6E+04

Total 5.7E+04 5.0E+08 69 6.0E+05

References1N-CLC-Z-00673, Table 1 - Source Terms2N-CLC-Z-00673, Table 4 - Submersible Pumps Absorbed Dose Rates3N-CLC-Z-00673, Attachment D - Alpha & Beta Dose Calculation4X-SD-Z-00001, Rev. 11, Saltstone Waste Acceptance Criteria, (6/14/12) - Attachments 8.3 & 8.4

Example Calculations

GammaCs-137 Dose Rate = (0.015 Ci/gal/1.98266E+01 Ci/gal)*(8.26E+03 Rad/hr) = 6 Rad/hr = 5.5E+04 Rad/yrBetaSrY-90 Dose Rate = (0.0851718 Ci/gal/7.1258E+01 Ci/gal)*(4.73E+04 Rad/hr) = 57 Rad/hr = 5.0E+05 Rad/yrAlphaAm-241 Dose Rate = (0.0009464 Ci/gal/2.74948E-01 Ci/gal)*(8.49E+02 Rad/hr) = 3 Rad/hr = 2.6E+04 Rad/yrAlphaPu-238 Dose Rate = (0.0009464 Ci/gal/7.05636E-02 Ci/gal)*(2.19E+02 Rad/hr) = 3 Rad/hr = 2.6E+04 Rad/yrTotal Dose Rate = (5.5E+04) + (5.0E+05) + (2.6E+04) + (2.6E+04) = 6.0E+05 Rad/yr

Conclusion

A wastewater pump submersed in 0.015 Ci/gal drainwater in the SDU6 drainwell is estimated to receive a total (alpha, beta and gamma; no neutron) dose rate of 6.0E+05 Rad/yr. This estimate is bounding as it assumes the Saltstone Facility design basis maximum Cs-137 concentration of 0.015 Ci/gal as well as assumes the pump is continuously submersed in a drainwell full of drainwater surrounded by the SDU6 full of grout.

Page 63: Calculation Continuation Sheet · 3.11 PNNL-15870,Rev. 1,Compendium of Material Composition Data for Radiation Transport Modeling,March 2011. 3.12 Savannah River Nuclear Solutions

OSR 19-260 (Rev 10-27-1993)

Calculation Continuation Sheet

Calculation No.N-CLC-Z-00027

Sheet No.63 of 63

Rev.0

Appendix Q – Total Absorbed Dose Estimate to SDU 6 Liner

N-CLC-Z-00013, Rev. 0, Integrated Absorbed Dose Calculation for the Polyethylene Liner Enclosing Vault 2, (9/26/05) estimates the 10,000-year dose to the SDU2 wall liner for 0.2 Ci/gal grout processing. The 10,000-year dose to a wall liner of similar thickness (i.e., 100 mil) around SDU6 can be reasonably estimated based on the N-CLC-Z-00013 results accounting for three factors:

1. Scaling up to account for the difference in size of the liner around SDU6 versus SDU22. Scaling down to account for the difference in SDU2 versus SDU6 Cs-137 content (i.e., 0.2 vs 0.015 Ci/gal)3. Scaling down to account for the additional shielding provided by the thicker SDU6 vs SDU2 concrete wall

Liner Size/Volume - the additional SDU6 height and radius make its liner 5.12x larger by volume (see table below).

SDU

Outer InnerLiner

Volume(cm3)

DifferenceHeight Liner Liner

(cm) Radius Radius

(cm) (cm)

SDU2 3.1416 609.6 2306.574 2306.32 2243892.374 n/a

SDU6 3.1416 1249.68 5758.434 5758.18 11484371.15 5.12

Cs-137 Source Term Content - the SDU2 Cs-137 content in N-CLC-Z-00013 is 13.33x greater than that which is planned for SDU6 (= 0.2 Ci/gal/0.015 Ci/gal). [NOTE: This same approach can be used for other Cs-137 concentrations (i.e., 0.03, 0.006, 0.0002) to simply arrive at a different factor with which to scale down.]

Shielding Provided By Thicker SDU6 Wall - SDU2's concrete wall is 8" thick. SDU6's concrete wall is 10" thick at the top and 24" thick at the bottom for an average thickness of 17". This additional 9" of concrete provides a shielding factor of 27.14 (see below).

Shielding Factor = et= e

(0.1444)(22.86)= 27.14 where

= linear attenuation coefficient for Cs-137 gammas in concrete = 0.1444 cm-1

t = additional concrete thickness = 9" = 22.86 cm

Reference: Shlein, B. et al, Handbook of Health Physics and Radiological Health, 3rd

Edition. Lippincott Williams & Wilkins, Philadelphia, 1998.

Results & Conclusion - N-CLC-Z-00013 reports the total integrated 10,000-year absorbed dose for the SDU2 wall liner as 213,290 Rad. Applying the above 3 factors as follows results in a total integrated 10,000-yr absorbed dose to a similar SDU6 wall liner as 3,019 Rad [= (213,290 Rad x 5.12)/ (13.33 x 27.14)].

This dose estimate to the wall liner can be further applied to a roof and floor liner as follows:

1. 3,019 Rad for a wall liner divided by its volume of 11484371.15 cc yields 0.000262879 Rad/cc.2. Volumefloor liner = (5758.18 cm)

2(0.254 cm) = 26457820.32 cc

Volumeroof liner = (5786.12 cm)2(0.254 cm) = 26715201.98 cc

3. Dosefloor liner = (26457820.32 cc)(0.000262879 Rad/cc) = 6,955 RadDoseroof liner = (26715201.98 cc)(0.000262879 Rad/cc) = 7,023 Rad

The total 10,000-year absorbed dose to the SDU6 liner would then be:

Dosetotal = Dosewall liner + Dosefloor liner + Doseroof liner = 3,019 + 6,955 + 7,023 = 16,997 Rad (~17,000 Rad)

Because 17,000 Rad to an SDU6 liner is still an order of magnitude less than the total 10,000-yr absorbed dose tothe SDU2 liner of 213,290 Rad, N-CLC-Z-00013 is considered bounding for SDU6.