Proceedings of the

17th International Conference

on Nuclear Engineering

- 2009 -

VOLUME 3

THERMAL HYDRAULICS

CURRENT ADVANCED REACTORS: PLANT DESIGNS,

CONSTRUCTION, WORKFORCE AND PUBLIC ACCEPTANCE

presented at

1 7th INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERINt.

JULY 12-16, 20M"

BRUSSELS, BELGIUM

sponsored h\

NUCLEAR ENGINEERING DIVISION, ASMf

THE JAPAN SOCIETY OF MECHANICAL ENGINEERS, JSMI

THE CHINESE NUCLEAR SOCIETY, CNS

A S M E

Three Park Avenue New York, N.Y. 10016

TIB/UB Hannover

133 265 544

CONTENTS

THERMAL HYDRAULICS

IC0NE17-75017 1

Water Spray Cooling of High-Temperature Steam Flow Through a Steam Turbine

Bypass Valve Line

R. S. Amano

IC0NE17-75035 11

Flow Visualization of Acoustic Resonance for Safety Relief Valves in Power Uprated BWRs

Keita Okuyama, Shirou Takahashi, Akinori Tamura, Koji Nishida, Masaya Ohtsuka, and

Masaaki Tsubaki

IC0NE17-75054 19

On Enhancing Water Heat-Transfer by Nanofluids

Alexander L. Shimkevich

ICOIME17-75060 23

Experimental Study on Application of Heat Transfer Enhancement Method Using Porous

Material With High PorosityTetsuaki Takeda and Koichi Ichirniya

ICONE17-75066 29A Study of Steam-Water Countercurrent Flow Model in TRACE Code

Yi-Hsiang Cheng, Chunkuan Shih, Jong-Rong Wang, and Hao-Tzu Lin

IC0NE17-75080 37

Development of Ex-Vessel Debris Agglomeration Mode Map for a LWR Severe

Accident Conditions

P. Kudinov and M. Davydov

ICONE17-75083 47

SCDAP/RELAP5 Analysis of Progression of Severe Accident in CANDU 6 Plant

Daniel Dupleac, Mirea Mladin, and Hie Prisecaru

IC0NE17-75085 59

Experimental Characterization of Hydraulics in EPR Control Rod Guide Assembly:EDF and AREVA Complementary Approaches

Philippe Dolleans, Sebastien Petitjean, Jean-Philippe Fontes, Elisabeth Longatte,Thierry Muller, Bruno Mezoul, and Benoft Migot

IC0NE17-75089 69

Mechanistic Prediction of CHF in Fuel Assembly Using the Subchannel Code CAPE

Ryo Yoshida, Kenji Yoshida, Isao Kataoka, and Masanori Naito

ICONE17-75091 77

Mechanistic Prediction of Void Fraction Distribution in BWR Fuel Assembly Using the

Subchannel Code CAPE

Kenji Yoshida, Ryo Yoshida, Isao Kataoka, and Masanori Naitoh

vii

IC0NE17-75097 85

Simulation of Containment Thermal-Hydraulic Phenomena in the Marviken Blowdown

Experiment With the CONTAIN and ASTEC CPA Codes

Ivo Kljenak and Borut Mavko

IC0IME17-75101 93

System-Core Thermal Hydraulic Interaction During a Reflood Phase of a Cold-LegLBLOCA in the Atlas Integral Effect Test Facility

Seok Cho, Hyun-Sik Park, Ki-Yong Choi, Kyong-Ho Kang, Yeon-Sik Kim, and

Won-Pil Baek

ICONE17-75104 105

Development and D3 Application of ABWR Feedwater System Model

Hui-Wen Huang, Chunkuan Shih, Hung-Chih Hung, Kai-Lan Chang, Shu-Chuan Chen,

Yu-Jen Pan, Mao-Sheng Tseng, Ming-Huei Chen, and Tsung-Chieh Cheng

ICONE17-75105 115

Thermohydraulic Studies of a New Passive Concept for Interim Storage:

Experiment and AnalysisBernard Buret, Jean Claude Argoud, and Judicael Sublon

ICONE17-75106 123

RELAP5 Evaluation vs. Marviken Full Scale Containment Experiments

Luca Facciolo and Tomas Almberger

ICONE17-75107 135

Analysis of IHX Vertical Position Effects in the Reactor Vessel of KALIMER-600

Ji-Woong Han, Jae-Hyuk Eoh, Tae-Ho Lee, and Seong-0 Kim

ICOIME17-75116 141

Numerical Calculations on Countercurrent Air-Water Flow in Small-Scale Models of a

PWR Hot Leg Using a VOF Model

Michio Murase, Yoichi Utanohara, Ikuo Kinoshita, Noritoshi Minami, and Akio Tomiyama

IC0NE17-75140 149

A Performance Test Result of Chordal Type Flowmeter Using High Reynolds Number

Facility in NMIJ

Noriyuki Furuichi, Yoshiya Terao, and Masaki Takamoto

ICONE17-75144 157

Experimental Study of the Influence of Roughness Change in a Piping on the

Flow Measurement

Yoshihisa Nishi, Yuzuru Eguchi, Takashi Nishihara, Izumi Kinoshita, Fumio Inada, and

Kazufumi Nagashima

ICONE17-75148 167

Maanshan PWR Loss of Flow Transients Analysis With TRACE

Jong-Rong Wang, Hao-Tzu Lin, Wei-Chen Wang, Yi-Hsiang Cheng, and Chunkuan Shih

ICONE17-75156 175

Differences in the Heat Transfer at the Core-Reflector Boundary of the PBMR

Due to the Use of Different Numerical Methods

Pieter S. du Toit and Onno Ubbink

viii

ICOIME17-75164 185

Experimental ECCS Sump Strainer Head Loss Testing and the Incorporation of CFD

Computed Source Terms for Pressurized Water Reactors

Stuart Cain, Fariba Gartland, James Bleigh, Andrew Johansson, and David Schowalter

ICONE17-75169 191

Hydraulic Modeling of Air-Entraining Vortex Formation During Flow Withdrawal From

Water Storage Tanks

Andrew Johansson, Mahadevan Padmanabhan, Stuart Cain, Bryan Meyer, and

David Schowalter

ICOIME17-75174 197

Comparison of Thermal Hydraulic Simulations of Beyond Design Basis Events Using the

MAAP4 and CENTS Computer CodesN. Reed LaBarge, Babara R. Baron, Raymond E. Schneider, and Mathew C. Jacob

ICONE17-75178 205

Assessment of Post-CHF Heat Transfer Models for the SPACE code

K. Y. Choi, B. J. Yun, H. S. Park, S. K. Moon, and K. D. Kim

ICONE17-75183 215

Transient Flow Field on Containment Floor Predicted by Two-Dimensional Shallow Water

Equation Solver

Young Seok Bang, Gil-Soo Lee, Byung-Gil Huh, Deog-Yeon Oh, and Sweng-Woong Woo

ICONE17-75205 223

Molten Pool Models Validation and Cross-Verification: CFD and SOCRAT Code

Alexander Filippov, Valery Strizhov, and Oleg Tarasov

ICONE17-75212 233

Heat Transfer to Supercritical Water in Vertical Annular Channel and 3-Rod Bundle

V. G. Razumovskiy, Eu. N. Pis'mennyy, A. Eu. Koloskov, and I. L. Pioro

ICOIME17-75221 239

Thermal-Hydraulic Evaluation of Joyo Fuel Subassembly With Local BlockageHiroaki Ohira and Misao Takamatsu

ICONE17-75269 247

Non-Linear Characteristics of Saturated and Subcooled Pool Boiling CHF for Various

Test Heater Configuration

Katsuya Fukuda and Qiusheng Liu

ICONE17-75273 257

A Comparative Study of Single-Phase, Two-Phase and Supercritical Natural Circulation in a

Rectangular LoopP. K. Vijayan, D. S. Pilkhwal, M. Sharma, D. Saha, and R. K. Sinha

ICONE17-75276 265

Thermal-Hydraulic Studies of the Steam Separation in Horizontal Steam Generator at

PGVTest Facility

Yuriy V. Parfenov, Oleg I. Melikhov, Vladimir I. Melikhov, and llya V. Elkin

ix

ICONE17-75282 269

The Hot Function Flow Characteristics of a Main Cooling Water System for the Nuclear

Fuel Test Loop Installed in HANARO

Young-Chul Park, Young-Seob Lee, and Dae-Young Chi

ICONE17-75284 277

Experimental Investigation of the Influence of Flow Obstacles on Post-Dryout Heat Transfer

in an Annulus

/. G. Anghel, H. Anglart, S. Hedberg, and S. Rydstrom

ICONE17-75287 287

Measurement and Analysis for Rewetting Velocity Under Post-BT Conditions During

Anticipated Operational Occurrence of BWR

Yasuteru Sibamoto, Yu Maruyama, and Hideo Nakamura

ICONE17-75293 297

Air Entrainment by Impinging Jets: Experimental Identification of the Key Phenomena and

Approaches for their Simulation in CFD

Martin Schmidtke, Dana Danciu, and Dirk Lucas

ICONE17-75296 307

The Further Evolution of the EREC-STRESA Web Database

Vladimir N. Blinkov and Mikhail V. Davydov

ICOIME17-75297 311

Verification of Discontinuous Random Walk Lagrangian Particle Tracking as a Tool to

Model Deposition in Annular Flow

Diana Caraghiaur Garrido and Henryk Anglart

ICONE17-75328 321

Comparative Analysis of Star-CCM, Star-CD, and CFX Codes for Free-Surface Flow

Simulation of the Windowless XT-ADS Spallation Target Water ExperimentA. Batta and A. G. Class

ICONE17-75350 329

Developemnt and Validation of Sacatri Code for Thermal- Hydraulic Analysis of the

CENM Triga Mark II

Ossama Merroun, Ahmed Al Mers, Marcelo A. Veloso, and Tarek El Bardouni

ICONE17-75358 337

Newly Developed Two-Tip Optical-Fiber Probe for Accurate Measurement of High-SpeedMicro-Droplets: Simultaneous Measurement of Their Velocities and Diameters

Keisuke Matsuda, Yusuke Ozawa, and Takayuki Saito

ICONE17-75361 345The Parameters Identification of Time-Delay Models of Heat Transfer Systems From

Input-Output MeasurementsGoran Simeunovic, Pavel Zitek, and Jan Chysky

ICOIME17-75380 353

Recent Hydrodynamics Improvements to the RELAP5-3D Code

Richard A. Riemke, Cliff B. Davis, and Richard R. Schultz

x

ICONE17-75383 359

Two-Phase Cross Flow Between Subchannels in a Tight-Lattice Rod Bundle

Weizhong Zhang, Hiroyuki Yoshida, and Kazuyuki Takase

ICONE17-75387 367

Photographic Study on Bubble Motion in Subcooled Pool BoilingTomio Okawa, Takahiro Harada, and Yuta Koutsusa

ICONE17-75390 375

Fragmentation of a Single Molten Metal Droplet Penetrating Sodium Pool:

Comparisons of Thermal and Hydrodynamic FragmentationZhi-gang Zhang and Ken-ichiro Sugiyama

IC0IME17-75399 381

RCS Pressure Predictions Under ATWS for Maanshan With MUR

Wen-Hsiung Wu, Chunkuan Shih, and Jong-Rong Wang

ICONE17-75401 389

RETRAN Application of Turbine Trip and Load Rejection of Startup Test Analysis for

Lungmen ABWR

Chen-Lin Li, Chiung-Wen Tsai, Chunkuan Shih, Jong-Rong Wang, and Su-Chin Chung

ICONE17-75432 395

Linear and Non-Linear Stability Analysis of a Supercritical Natural Circulation Loop

Manish Sharma, P. K. Vijayan, D. S. Pilkhwal, D. Saha, and R. K. Sinha

IC0NE17-75463 405

Survey on Methodologies for Thermal-Hydraulics System Codes Uncertainty Assessment

Mohammad Pourgol-Mohammad and Kamran Sepanloo

ICONE17-75484 415

Thermo-Hydraulic Calculation and Safety Analysis of the Tehran Research Reactor

J. Jafari, M. K. Firuzjaee, S. Khakshournia, K. Sepanloo, and F. D'Auria

ICONE17-75516 423

Modeling of Thermal Hydraulics Features of Top Water Reflood Experiment

PARAMETER-SF3 Using S0CRAT/V2 Code

Arcadii E. Kisselev, Valeril F. Strizhov, Alexander D. Vasiliev, Vladimir I. Nalivayev, and

Nikolay Ya. Parshin

1COIME17-75534 433

Thermo-Hydraulic Design of Westinghouse 4-Loop Reactor Core by COBRA-EN Code

J. Jafari, B. Kalagar, E. Abdi Aghdam, and F. D'Auria

ICONE17-75561 441

Experimental Study on Gas Entrainment Due to Non-Stationary Vortex in a Sodium Cooled

Fast Reactor: Comparison of Onset Conditions Between Sodium and Water

Nobuyuki Kimura, Toshiki Ezure, Hiroyuki Miyakoshi, Hideki Kamide, and

Takeshi Fukuda

xi

IC0NE17-75563 ,449

Analysis of Severe Accidents in VVER-1000 Reactors Using the Integral Code ASTEC

Polina Tusheva, Nils Reinke, Eberhard Altstadt, Frank Schaefer, Frank-Peter Weiss,

and Antonio Hurtado

ICONE17-75567 459

Measurement of Steam Generator or Reactor Vessel Moisture Carryover Using a

Non-Radioactive Chemical Tracer

Robert Fournier, Michael Thibodeau, and Charles T. French

ICONE17-75575 469

Study on Thermal Striping at UIS of Advanced Loop Type Fast Reactor:

Water Experiment Using a 1/3 Scale 60 Degree Sector Model

Jun Kobayashi, Nobuyuki Kimura, Akira Tobita, Hideki Kamide, Osamu Watanabe, and

Kazuhiro Oyama

ICONE17-75582 479

Results of a Steam-Water Experiment Simulating Two-Phase Flow in Pressurizer

Spray PipingToru Oumaya, Akira Nakamura, and Nobuyuki Takenaka

ICONE17-75589 487

Flow Regime Classification and Transition of Flow Boiling Through Porous Channel

Bofeng Bai, Xiaojie Zhang, Maolong Liu, and Su Wang

ICONE17-75590 495

An Experimental Study on Air-Water Two-Phase Flow in Pebble Beds

Bofeng Bai, Maolong Liu, and Xiaojie Zhang

ICONE17-75594 503

Post-Test Investigations of BFBT Critical Power Tests With Trace

Marc Thieme, Wolfgang Tietsch, Rafael Macian, and Victor Hugo Sanchez Espinoza

ICONE17-75611, 515

Dynamics Integrated Valve Analysis for Gas Turbine SystemSeong G. Kang and Kune Y. Suh

ICONE17-75620 521

Characteristics of Direct ECC Bypass Phenomena on the Accident Simulation of Late-Phase

Reflood in the APR1400

Kyoung-Ho Kang, Hyun-Sik Park, Ki-Yong Choi, Seok Cho, Nam-Hyun Choi,

Byong-Jo Yun, Won-Pil Baek, and Yeon-Sik Kim

ICOIME17-75629 529

Measurement of Natural Circulation Two-Phase Flow by Hybrid Doppler Contrapropagatingand Pulse Echo Ultrasonic Techniques

Jose L. H, Faccini, Jen-Shih Chang, Glenn D. Harvel, Paulo A. B. De Sampaio, and

Jian Su

ICONE17-75638 539

Multidimensional Analysis of UPTF Upper Plenum Injection Test With MARS-KS Code

Kyung Won Lee, Yong Jin Cho, and Seung Hoon Ahn

xii

ICONE17-75641 545

Examination of a Simplified Thermal-Hydraulic Program for a PWR Core Protection SystemWang-Kee In, Tae-Hyun Chun, and Seung-Yeob Baeg

ICONE17-75655 553

New Method for Numerical Prediction of Water Hammer With Column Separation:

Comparison With Experiment and the Relap5 ProgramAdam Adamkowski, Mariusz Lewandowski, and Jerzy Marcinkiewicz

ICONE17-75657 561

Blind and Post Test Calculation of the Hydrogen Stratification Experiment HM-2 With the

Containment Code System COCOSYS

Joerg Burkhardt and Marco K. Koch

1CONE17-75666 567

Optimizing the Initial Pressure of Accumulators for the Atucha 2 NPP Using an

Optimization MethodN. Muellner, A. Del Nevo, M. Cherubini, F. D'Auria, and O. Mazzantini

ICOIME17-75667 575

Two-Energy Modeling of Heat Conduction in a Heterogeneous Spherical Fuel Element

Carlos V. Pessoa, Claudio L. de Oliveira, and Jian Su

ICOIME17-75705 585

Parameter Adaptation Techniques for the Best-Estimate Thermal-Hydraulic Code ATHLET

Alexander Kerner, Anselm Schaefer, and Kan Chen

ICONE17-75723 595

Prony's Method for BWR Stability Analysis

Rogelio Castillo-Duran, Javier Ortiz-Villafuerte, Jose Ramon Ramirez-Sanchez,Javier C. Palacios-Hernandez, Gabriel Calleros-Micheland, and Carlos Filio-Ldpez

ICOIME17-75724 599

Recent Improvements to the Multi-Dimensional Semi-Implicit Two-PhaseFlow Solver, CUPID

H. K. Cho, I. K. Park, H. D. Lee, and J. J. Jeong

ICONE17-75737 609

Studies of Flow Diversion Due to a Ballooned Pin

Yiyun Jessy Zeng, Colin P. Hale, Simon P. Walker, and Geoffrey F. Hewitt

ICOIME17-75738 619

Study on Subcooled Flow Boiling Heat Transfer Under Vibration Conditions

Hiroyasu Ohtake, Naoki Uchida, and Yasuo Koizumi

IC0IME17-75763 625

Transient Response of BWR Core Flow During Simulated Generator Load Rejection Event

Masahiro Furuya, Takashi Hara, and Shinya Mizokami

ICOISIE17-75764 633

Effect of Nanofluid on the Film Boiling Behavior at Vapor Film CollapseTakahiro Aral and Masahiro Furuya

xiii

IC0INIE17-75772 639

Steady Propagation of the Vaporization Front in Metastable Liquid

Sergey Aktershev and Valeryi Ovchinnikov

IC0NE17-75775 645

Simulation of a Once-Through, Helical-Coiled Steam Generator of High TemperatureGas-Cooled Reactor

Jinliang Ye, Yangping Zhou, Xiaoming Chen, Yuanle Ma, Fu Li, and Yujie Dong

ICONE17-75777 651

Thermal-Hydraulic Characteristics of the 250MW Pebble-Bed Modular High TemperatureGas-Cooled Reactor in Start-Up and Shutdown Processes

Xunxiang Hu, Yujie Dong, Yanhua Zheng, Yangping Zhou, and Lei Shi

ICONE17-75790 ,659

Recent Design Technologies of Moisture Separator Reheater

Jun Manabe, Jiro Kasahara, Toshiki Kojima, and Issaku Fujita

ICONE17-75816 671

Computational Fluid Dynamics Modeling of PWR Steam Generator Sludge

Collector/Loose Parts Weir

Chunyun Wang, Jason Burr, and Naeem Karim

ICONE17-75818 679

Subcooled Boiling Heat Transfer in a Short Vertical SUS304-Tube at High Liquid

Reynolds NumberKoichi Hata and Suguru Masuzaki

ICONE17-75838 695

Addressing Boron Dilution Scenario Through RELAP5/3.3 Analysis of PWR SB LOCA

Patricia Pla, Regina Galetti, Francesco D'Auria, Francesc Reventos, Carlo Parisi,Walter Giannotti, Alessandro Dei Nevo, Nikoiaus Muellner, Marco Cherubini, and

Giorgio Galassi

ICONE17-75845 705

Numerical Solution on Spherical Vacuum Bubble Collapse Using MPS Method

Wenxi Tian, Suizheng Qiu, Guanghui Su, and Yoshiaki Oka

ICOIME17-75848 713

Experimental Study on Thermal-Hydraulic Performance of Single-Phase Water Flow in

Narrow Rectangular Channel

Mei Wang, Yan Wen, Suizheng Qiu, Guanghui Su, and Weifeng Ni

ICONE17-75879 721

Development of Best-Estimate ECCS Evaluation Methodology for APR1400

Seok-Ho Lee, Mun-Soo Kim, and Han-Gon Kim

ICONE17-75880 729

Measurement of Surface Heat Fiux and Surface Temperature in Nucleate Pool Boiling

Using Micro-ThermocouplesWei Liu and Kazuyuki Takase

xiv

ICONE17-75893 735

Modeling of the Upper Head of a Pressurized Water Reactor During Transient OperationKlaus Dubiel and Nelson Macken

ICOIME17-75901 741

ABWR Containment Analysis Model Qualification Using the GOTHIC Code

J. Douglass, T. George, N. Jain, N. Barnett, D. Gallagher, R. Ofstun, and B. Loehlein

ICOIME17-75937 747

Effectiveness of RCS Depressurization Strategy for Severe Accident ManagementChangwook Huh, Namduk Suh, and Goon-Cherl Park

ICONE17-75954 755

Derivation and Analysis of the Criterion for Onset of Density Wave Oscillation in Tubes and

Channels With Riser

Yu. Kornienko

ICONE17-75960 763

Analysis of Thermal Effects in a Cavitating Orifice Using Rayleigh Equation and ExperimentsMaria Grazia De Giorgi, Daniela Bello, and Antonio Ficarella

ICONE17-75962 775

High-Cycle Thermal Fatigue in Mixing Tees: New Large-Eddy Simulations Validated AgainstNew Data Obtained by PIV in the Vattenfall Experiment

Ylva Odemark, Torbjorn M. Green, Kristian Angele, Johan Westin, Farid Alavyoon, and

Staffan Lundstrom

ICONE17-75980 787

Mini-Channel Supercritical CO2 Heat Transfer Measurements for Brayton Cycle

RegeneratorsAlan Kruizenga, Mark Anderson, and Michael Corradini

ICONE17-75993 793

Comparison and Improvements of Correlations for Fiim Boiling in Tubes

E.-L. Pelletier, L. K. H, Leung, A. Teyssedou, and Ft. Girard

ICOIME17-75995 801

Experimental Investigation on Two-Phase Flow Distribution in Multi-Channel Manifold With

Two Radial Inlets

Liping Pang, Baomin Sun, and Bo Wang

ICOINIE17-76022 807

Progress in Developing an Improved Empirical Heat Transfer Equation for Use in Connection

With Advanced Nuclear Reactors Cooled by Water at Supercritical Pressure

J. Derek Jackson

ICON E17-76034 821

The Water Ingress Mass Analysis in the Steam Generator Heat-Exchange Tube RuptureAccident of High Temperature Gas-Cooled Reactor

Van Wang, Yanhua Zheng, Fu Li, Lei Shi, and Zhiwei Zhou

xv

ICON E17-76044 829

Development of WC0BRA/TRAC-TF2 Computer Code: Coupling of the 3D Module

(COBRA-TF) With the 1D Module of TRAC-PF1/MOD2

Cesare Frepoli, Kastuhiro Ohkawa, and Mitch Nissley

1COIME17-76056 843

International Training Program in Support of Safety Analysis: 3D S.UN.COP - Scaling,

Uncertainty and 3D Thermal-Hydraulics/Neutronkinetics Coupled Codes Seminars

Alessandro Petruzzi, Francesco D'Auria, Tomislav Bajs, and Francesc Reventos

ICONE17-76057 853

CIAU Methodology and BEPU ApplicationsA. Petruzzi and F. D'Auria

CURRENT ADVANCES IN REACTORS: PLANT DESIGN, CONSTRUCTION,

WORKFORCE AND PUBLIC ACCEPTANCE

ICONE17-75184 863

General Safety Design Approach and Main Safety Features of ATMEA1

Eric Mathet, Philippe Lauret, Takahashi Kanagawa, Gerard Castello, and Yasuhiko Okabe

ICONE17-75275 869

Nuclear Disciplines in Response to Industry and Regulatory Needs Through the EuropeanNuclear Education Network Association

Joseph Safieh, Peter P. De Regge, and Ryoko Ksuumi

ICONE17-75280 885

An Integrated Approach to Human System Interface Design in New Nuclear Power Plants

Jose Manuel Viguera, Alfonso Jimenez, and Juan Antonio Burillo

ICONE17-75314 893

Robustness of the MSHIM Operation and Control Strategy in the AP1000 Design

Keith J. Drudy, Toshio Morita, and Barbara T. Connelley

ICONE17-75408 905

Use of PRA in the Design of the Westinghouse AP1000 Plant

Robert J. Lutz, James H. Scobel, Richard G. Anderson, and Terry Schulz

ICONE17-75412 911

AP1000 Breaking the Dependence on Site Characteristics

(Electrical Grid and Cooling Water)Richard G. Anderson, Terry L. Schulz, and Daniel T. McLaughlin

ICONE17-75476 919

Concrete Shrinkage Taken Into Account as Crack Width Assessment

Etienne Gallitre, Pierre Alain Naze, and Pierre Labbe

ICONE17-75683 923

AP1000: Ansaldo Participation to Engineering and Construction Activities for China Plant

Monica Frogheri and Gianfranco Saiu

xvi

ICONE17-75689 933

Impact of the External Factors in the Nuclear Field: A Comparison Between Small Medium

Reactors vs. Large Reactors

Mauro Mancini, Giorgio Locateili, and Serena Tammaro

ICONE17-75741 945

Cost and Profitability Analysis of Modular SMRs in Different Deployment Scenarios

Sara Boarin and Marco E. Ricotti

ICOIME17-75830 953

Features of Design and Results of Function Tests at Tomari Unit 3

Ichiro Sakai, Takashi Yano, Takashi Takemura, and Kousei Yamada

ICONE17-75836 961

The Study for Installation of the Autocatalytic Flammability Control System in New

ABWR Plants

Haruki Suzuki, Taichi Takii, and Shingo Oda

ICONE17-75851 969

Design and Development of Diverse Safety Rod and Its Drive Mechanism for PFBR

R. Vijayashree, P. ChellaPandi, K. Natesan, S. Jalaldeen, S. C. Chetal, and Baidev Raj

ICOIME17-75853 979

Testing and Qualification of Diverse Safety Rod and Its Drive Mechanism for PFBR

R. Vijayashree, R. Veerasamy, Sudheer Patri, S. Suresh Kumar, S. C. S. P. Kumar Krovvidi,S. K. Dash, T. Logaiyan, N. Ravichandran, S. Chandramouli, K. K. Rajan,

Indranil Banerjee, and R. Dhanasekaran

ICOIME17-75864 987

Management of Construction at Latest ABWR "SHIMANE 3"

Norihiko Hirata, Katsumi Fushiki, Masahide Nishimoto, and Kouichi Murayama

ICOIME17-75865 993

Westinghouse AP1000 Power Production Reliability Classification MethodologyMatthew C. Evans and Terry L Schulz

1COIME17-76055 1003

Dealing With External Factors in the Electricity Generation Sector: Nuclear vs. Other

Baseload TechnologiesMauro Mancini, Giorgio Locateili, and Serena Tammaro

Author Index 1013

xvii