Proceedings of the

21 st International Conference on

Nuclear Engineering

- 2013 -

volume 3

NUCLEAR SAFETY AND SECURITY

CODES, STANDARDS, LICENSING AND REGULATORY ISSUES

COMPUTATIONAL FLUID DYNAMICS (CFD) AND COUPLED CODES

presented at

2013 21st INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING

JULY 29-AUGUST 2, 2013

CHENGDU, CHINA

sponsored byTHE NUCLEAR ENGINEERING DIVISION, ASME

THE JAPAN SOCIETY OF MECHANICAL ENGINEERS, JSME

THE CHINESE NUCLEAR SOCIETY, CNS

ASME

Two Park Avenue * NewYork, N.Y. 10016

CONTENTS

NUCLEAR SAFETY AND SECURITY

ICONE21 -15034 V003T06A001

Preliminary Study of the Application of PEFS on PCWA

Jianhua Cao, Xiangang Fu, Xianghui Lu, and Xiaohua Jiang

ICONE21-15088 V003T06A002

The Development of a Mechanistic Model of MCCI Under Severe Accidents

Wei Wei, Kelin Qi, Fuchang Shan, Yanfang Chen, and Fude Guo

ICONE21-15117 V003T06A003

A Proposal on Ultimate Safety Disposal of High Level Radioactive Wastes

Hidekazu Yoshikawa

ICONE21 -15125 V003T06A004

Fast On-Line Source Term Estimation of Non-Constant Releases in Nuclear Accident Scenario

Using Extended Kalman Filter

Pierre Tricard, Sheng Fang, Jianlong Wang, Hong Li, Jingyuan Qu, Jiejuan Tong, and

Dong Fang

ICONE21-15191 V003T06A005

Analysis of Factors Influencing Compressive Bearing Capacity of Nuclear Containment

Gangling Hou, Chenning Song, Tianshu Song, and Guoliang Zhou

ICONE21 -15204 V003T06A006

Live Experimental Results of Melt Pool Behaviour in the PWR Lower Head With Insulated

Upper Lid and External CoolingXiaoyang Gaus-Liu and Alexei Miassoedov

ICONE21 -15242 V003T06A007

The Human Reliability Analysis in Fire PSA Using Spar-H Method

Yao Wang

ICONE21 -15253 V003T06A008

Research for Crossing Strait Transportation Accident of Nuclear Fuel Assemblies

Xiaoxiao Xu, Xuexin Wang, Jiangang Zhang, Chaoduan Li, Fan Gao, Rongyao Tang,Lian Cao, and Bing Wen

ICOIME21 -15258 V003T06A009

Reliability Analysis for Power Supply System in a Typical Reprocessing Facility Based on

GO MethodologyRenze Wang, Zongyang Feng, and Pengbo Li

ICONE21 -15268 V003T06A010

The Research on Core Melting Process: Oxidation

Jun Wang, Wenxi Tian, Jianan Lu, Yingying Ma, Guanghui Su, and Suizheng Qiu

ICONE21 -15299 V003T06A011

PSA Conservatism Analysis and Quantification for the LOFW Accident

Tony X. Kong, Chunrui Deng, Ivan Vrbanic, and Ivica Basic

v

ICONE21 -15307 V003T06A012

First-Order and Second-Order Sensitivity Studies of ARCON96 for Ground Release Mode

Yun Liu, Sheng Fang, Hong Li, Dong Fang, Jiejuan Tong, and Jingyuan Qu

ICONE21-15314 V003T06A013

Study on the Influence of Safety Injection Rate on the Process of SBLOCA

He Hui and Liang-ming Pan

ICOIME21-15361 V003T06A014

Sensitivity Studies on the Influence of Shutdown Control Assembly Banks Arrangement in

Rod Control Assembly Banks Withdrawal From a Subcritical Condition

Dawei Cui, Yanhua Cheng, Yulong Mao, and Jun Chen

ICONE21-15437 V003T06A015

Research on Fault Diagnosis Approach Based on the Signed Directed Graph Model for

Nuclear Power Plant

Zhen Liu, Yong-kuo Liu, Xiao-tian Wu, and Xian Zeng

ICONE21 -15449 V003T06A016

Numerical Simulation of Electromagnetic Field in the Cold Crucible

Jinlong Zhang and Pengfei Li

ICONE21-15462 V003T06A017

Improvement on Dual Energy CT Reconstruction Method With Reduced Data

Yuanyuan Liu, Peng Zheng, and Chunming Zhang

ICONE21 -15529 V003T06A018

Heat Sink Issue: A Specific Safety Issue for NPP Site Selection and Evaluation in the Warm

Countries With Extreme Climatic Conditions

Andrei Rodionov and Jean-Marie Mattei

ICONE21-15553 V003T06A019

TRACE Validation Against LOCA Transients Performed on Fix-ll FacilityXiao Hu, Mian Xing, and Weimin Ma

ICONE21-15641 V003T06A020

Spent Fuel Pool Accidents in a Nordic BWR

Niina E. Kononen

ICONE21-15670 V003T06A021

Simulation on the Decontamination Efficiency and Factor of Radioactive Waste Water

Disposed by Supersonic Wave

Guangxia Zuo, Bin He, Rusong Li, Fengmei Yu, and Wenyan Ma

ICONE21 -15687 V003T06A022

Preliminary Study on the Primary Side Structure Design Improvement Based on CPR1000

Jianshu Lin, Chengjun Zhuang, Jun Cui, Ting Wang, and Zhenhua Zhang

ICONE21-15774 V003T06A023

Characteristic Analysis of Supercritical Water-Cooled Reactor During Uncontrolled CR

Withdrawal at Normal Operation Transient

Wanxu Cheng, Tao Zhou, Liang Liu, Mingqiang Song, and Bangyang Xia

vi

ICOIME21 -15814 V003T06A024

3-D Base Control Systems for the Seismic Protection of Power Plant Equipment and BuildingsPeter Nawrotzki and Weiqiang Wang

ICONE21-15828 V003T06A025

An Implementation of DFM for Reliability Modeling and Analyzing of AP1000 FWCS

Jiubo Yin, Jianyuan Cao, andXu Wang

1CONE21-15833 V003T06A026

An Investigation of Deterministic Realistic Method for LBLOCA Mass and Energy Release

Evaluation for CPR1000 NPPs

Jianshu Lin, Chengjun Zhuang, Jinzhen Leng, Ting Wang, and Zhang Zhenhua

ICONE21-15879 V003T06A027

Fretting Wear Behavior of NC30Fe in Distilled Water and Hydrazine Solution

Hong Guo, Pengdi Ren, Xiaoyu Zhang, Guangxiong Chen, and Yi Ye

ICONE21-15885 V003T06A028

Measurement of Gas Temperature in a Large Enclosure by Tunable Diode Laser

Absorption SpectroscopyJun Tian, Zulong Hao, Yu Yu, Huagui Li, Jianjun He, Yilin Zhang, and Jiayuan Li

ICONE21 -15955 V003T06A029

Thermal-Hydraulic Simulations of Guard Containment in Depressurization Accidents of a

Gas-Cooled Fast Reactor

Zhanjie Xu and Thomas Jordan

ICONE21 -15965 V003T06A030

A Review on Application of Technologies for Measuring Hydrogen Concentration in

Containment

Sha Luo, Shaobo Wang, Liang Qin, and Feng Pang

ICONE21 -15968 V003T06A031

The Analysis of AP1000 Depressurization During Small Break LOCA

Shuangji He

ICONE21 -15970 V003T06A032

Device for Measuring Hydrogen Concentration in Containment During Severe Accident

Sha Luo, Shaobo Wang, Liang Qin, and Feng Pang

ICONE21-15993 V003T06A033

Design of a Low Vulnerability Electronic Fiber Optic Seal SystemYuming Di, Quanhu Zhang, Guangxia Zuo, Feng Han, Ronghua Chen, Yonggang Huo, and

Peng Xu

ICONE21 -16007 V003T06A034

Analysis of Liquid Sloshing in an In-Containment Refueling Water Storage Tank for AP1000

Yu Liu, Daogang Lu, Junjie Dang, Licun Wu, and Wenhui Ma

ICOIME21 -16058 V003T06A035

The Development and Application of PWR Severe Accident Simulation Model

Yanfang Chen, Zhengquan Xie, Xusheng Lin, Fuchang Shan, Wei Wei, and Fude Guo

vii

ICONE21 -16092 V003T06A036

A Comparison in the Accuracy of Mapping Nuclear Fallout Patterns Using DELFIC and Several

Modified Models Based on DELFIC

Jian-bo Shang, Quan-lin Shi, and Qun-shu Wang

ICOIME21 -16165 V003T06A037

Safety Analysis on Mitigation Overpressure ATWS JDH in VVER-1000 NPP

Ting Qi and Changjiang Yang

ICONE21-16171 V003T06A038

CFD Analysis on Hydrogen Risk in Subcompartment of the Containment

Zhiqiang Zou, Jian Deng, and Yu Zhang

ICONE21-16334 V003T06A039

Application of Integrated Safety Assessment Methodology to Feed and Bleed SequencesC. Queral, J. Mula, J. Gomez-Magan, J. Gil, I. Fernandez, E. Melendez, M. Sanchez-Perea,

and J. Hortal

ICONE21-16348 V003T06A040

Effects of Break Location and Time Uncertainties in Small-Break and Medium-Break LOCA

Sequences With Unavailability of HPSI

J. Gonzalez-Cadelo, C. Queral, and J. Montero-Mayorga

ICONE21 -16369 V003T06A041

Damage Domains Calculation Associated With Multiple Damages in a Steam Generator Tube

Rupture Dynamic Event Tree

Gonzalo Jimenez, Cesar Queral, Maria Jose Rebollo-Mena, Javier Magan, Ivan Fernandez,Jesus Gil, Miguel Sanchez-Perea, Jose Maria Izquierdo, Enrique Melendez, and

Javier Hortal

ICONE21 -16398 V003T06A042The Fault Tree Analysis on Auxiliary Feedwater Pump Room Ventilation System in

Pressurized Water Reactor Power

Yang Li and Chen Hang

ICONE21-16470 V003T06A043

Experimental Study of Feed Water Level Decreasing Effect on VVER Steam Generator Model

Operation in Condensation Mode

A. V. Morozov, O. V. Remizov, and A. S. Soshkina

ICONE21 -16510 V003T06A044

Experimental Investigation of CCFL in Large Diameter Hot-Leg GeometrySuleiman Al Issa and Rafael Macian-Juan

ICONE21 -16526 V003T06A045

A Post Accident Safety Analysis Report of the Fukushima Accident:

Future Direction of Evacuation - Lessons Learned

Genn Saji

ICONE21-16671 V003T06A046

Analysis of Isolation Condenser Behavior by TRACG Code

Yoshihiko Ishii, Naoyuki Nakadozono, and Hitoshi Ochi

viii

ICONE21-16683

Safety Evaluation of Nuclear Plant Fire Using CFD AnalysisAkihiro Matsuda, Takashi Ishibashi, and Susumu Tsuchino

V003T06A047

ICONE21-16831 V003T06A048ALWR PRA Standard DevelopmentJames R. Chapman

ICONE21 -16832 V003T06A049

Fire PRA InsightsJames R. Chapman

ICONE21-16834 V003T06A050

Risk Insights and Use Based on Fukushima Accident

James R. Chapman, K. Raymond Fine, and C. Rick Grantom

CODES, STANDARDS, LICENSING, AND REGULATORY ISSUES

ICONE21-15064 V003T07A001

Preliminary Research on the Elimination of OBE in the Seismic Design of NPP

Qiang Li and Jian Zhang

ICONE21-15086 V003T07A002

Codes Comparison and Analysis of Weld Cladding Ultrasonic Testing in Nuclear Power Plants

Zhimin Zhong, Jian Min, and Kai Li

ICONE21 -15176 V003T07A003

Historical Perspectives and Insights on ACRS Review of AP1000 Design Certification

Hossein Nourbakhsh, Weidong Wang, Harold Ray, and Thomas Kress

ICONE21 -15291 V003T07A004

A Study of Rules of Material Groupings in ASME IX QW-420 by Decision Tree Method

Lifeng Guo, Yaochun Zhang, Libo Shi, and An Dong

ICONE21-15404 V003T07A005

Proposed Improvements of the ASME B&PV Code and Future Directions of CIWG

Jinquan Van, Yinbiao He, Gang Li, and Hao Yu

ICONE21-15412 V003T07A006

Study and Compare on Classification and Management Requirements of Domestic and

Foreign Research Reactors

Haiyang Wang, Chenxiu Song, and Quanyuan Gao

ICONE21-15419 V003T07A007

Comparison of PTS Guides for Reactor Pressure Vessel Integrity Assessment

Milan Brumovsky

ICONE21-15439 V003T07A008

Lessons Learned From Automation of Nonconformance Reporting (NCR) Process at

Los Alamos National Laboratory (LANL)Shyla A. McFarland, Gary Sandquist, Taunia S. Van Valkenburg, Daniel J. Tepley, and

Ernie F. Petru

ix

ICONE21 -15476 V003T07A009

Consideration on Selection of Design Codes and Standards for China Fusion EngineeringTesting Reactor

Guoqing Li, Chao Xing, Yexi Kang, and Xiaozhen Li

ICONE21 -15488 V003T07A010

Quality Assurance for a Nuclear Power Plant Simulator by Applying Standards for

Safety-Critical Software

Cheng Ye, Chao Ni, Tian Zheng, Zhicheng Zhang, and Ronghua Zhang

ICONE21-15491 V003T07A011

Comparison of Different Acceptance Standard for Radiographic Rounded Indications in Welds

Cong Wang, GuoXiang Tang, JiaGuan Zhao, and HengLiang Yang

ICOIME21-15551 V003T07A012

Exploration of China Nuclear Power Standard System DevelopmentJinquan Yan, Shenjie Gu, and Lin Tian

ICONE21-15591 V003T07A013

Inspection Qualification of Ultrasonic Inspection for RPV Safe End Narrow Gap Welding With

Visualization of Laser Ultrasonic Detection Technology and Computerized Ultrasonic Simulation

ShuXian Yuan, Ming Li, GuanBing Ma, XueZhu Xiao, and TianMing Lv

ICONE21-15842 V003T07A014

Application of RSE-M2010 on In-Service Inspection of Taishan EPR Project

Xueliang Zhang, Chunbing Shao, Ximing Tang, Cheng Yang, and Huixing Feng

ICONE21-16121 V003T07A015

Study on the Nonradioactive Environmental Impact Assessments for Chinese

Nuclear Power Plants

Xinyu Wei, Hongbin Ma, Xiaowei Xiong, Duanjie Yang, and Zhaorong Shang

ICONE21-16372 V003T07A016

Nuclear Power Plant Design Verification Based on the AnalyzerHanlin Wang, Mingguang Zheng, and Tunfeng Qi

ICONE21-16375 V003T07A017

RCC-M and RSE-M: A Set of Consistent Codes for PWR Design and OperationClaude Faidy

ICONE21 -16376 V003T07A018

Major Improvements of French Mechanical Nuclear Components Codes:

RCC-M, RCC-MRx, and RSE-M

Claude Faidy

ICONE21 -16379 V003T07A019

Fatigue of Stainless Steel Components: Toward Codified Rules ImprovementsClaude Faidy

ICOIME21-16392 V003T07A020

Selection of Chemical Hazard Prediction Models for Plant Safety and Control Room

Habitability Evaluations

Mary C. Richmond, Ping K. Wan, Brady P. Dague, and Kyra W. Davis

x

ICONE21 -16393 V003T07A021

Water Use Management Challenges in Power Generation

Kit Y. Ng and Ping K. Wan

ICONE21 -16718 V003T07A022

Off-Site Emergency Response of AP1000

Xiaodong Huang and Fenglei Du

ICONE21 -16788 V003T07A023

Towards the Development of Shutdown Emergency Operating Procedures for Nuclear

Power Reactors

Isaac Malgas

ICONE21-16792 V003T07A024

More on Design Evaluation of Nuclear Power Piping Subjected to Time-History Dynamic Loads

According to ASME B&PV III

Lingfu Zeng and Lennart G. Jansson

ICONE21 -16810 V003T07A025

An Introduction to RCC-C: An AFCEN Code for Design and Construction of

PWR Fuel Assemblies

Christine Vauglin, Marc Ton-That, Morello Sperandio, and Denis Buisine

ICONE21 -16827 V003T07A026

Introduction to KEPIC (Korea Electric Power Industry Code)

Myoung-Sung Sohn, Hyun-Jae Joo, Hoon-Seok Byun, and Jong-Hae Kim

COMPUTATIONAL FLUID DYNAMICS (CFD) AND COUPLED CODES

ICONE21 -15007 V003T10A001

Analysis of Main Steam Line Break Accident at Hot Shutdown State Using a Coupled Method

Dawei Cui, Jinzhen Leng, and Jun Chen

ICONE21-15014 V003T10A002

A Study of GOTHIC 8.0 Code Application to AP1000 Containment ResponseGuodong Wang and Zhe Wang

ICONE21 -15040 V003T10A003

The Design and CFD Simulation of a New Spent Fuel Pool Passive Cooling SystemCheng Ye, Minglu Wang, Mingguang Zheng, Zhengqin Xiong, and Ronghua Zhang

ICONE21-15049 V003T10A004

Flow Characteristics of Fuel Bundle With New Mixing Vane DesignWenchi Yu, Zhengzheng Pang, Yuemin Zhou, Weicai Li, and Xiaoming Chen

ICONE21-15051 V003T10A005

Development and Validation of Two-Way Fluid-Particle Coupling in Turbulent Flows

for a CFD Code

Jianjun Xiao, Anatoly Svishchev, and Thomas Jordan

ICONE21 -15124 V003T10A006

Preliminary Analysis of Two-Phase Flow in a Steam Generator Using CUPID-SG

Hyungrae Kim, Soo Hyoung Kim, Seung-Jun Lee, Ik Kyu Park, and Han Young Yoon

xi

ICONE21-15128 V003T10A007

Numerical Investigation of Two Phase Flow and Heat Transfer Characteristics of Passive

Containment Cooling SystemJia-Jia Deng, Liang-Ming Pan, and Mei-Qiang Kang

ICONE21 -15163 V003T10A008

Experimental Analyses by SIMMER-III on Duct-Wall Failure and Fuel Discharge/RelocationBehavior

Hidemasa Yamano and Yoshiharu Tobita

ICOIME21 -15180 V003T10A009

Fluid-Structure Coupling Analysis for the Flow Distribution Device of Nuclear Reactor Internals

Mingqian Zhang, Yuangang Duan, Xiaobing Ran, and Yanwu Liu

ICONE21 -15187 V003T10A010

Conservative Front-Tracking Method for 2-Dimensional Deformable Drops

Lei Chang and Yanning Yang

ICONE21-15194 V003T10A011

Numerical Study on the Influence of Non-uniform Wall Roughness on Vortex Structure in

Sparse Lattice

Hongguang Xiao, Yangwei Zhang, Binghuo YAN, and Wenzhen Chen

ICONE21-15198 V003T10A012

Development and Application of Single-Phase CFD Methodology for Estimating Flow

Field in Rod Bundles

Fujun Gan, Libing Zhu, Jiazheng Liu, Yixiong Zheng, and Xing Tong

ICONE21 -15202 V003T10A013

Numerical Simulation of Quasi Periodic Large Scale Vortices in Rod Bundles With

Non-Uniform Wall RoughnessGaojie Hu, Lei Yu, Yangwei Zhang, and Binghuo Yan

ICONE21-15226 V003T10A014

Analysis of the Thermal Hydraulic Phenomena Caused by Steam Jets in AP1000 Containment

Yingqiu Hu, Yu Yu, Fenglei Niu, Xin Liu, and Ruichang Zhao

ICOIME21 -15339 V003T10A015

Multiphase Flow Simulation of Subcooled Boiling Using the N-Phase Approach in TransAT

S. Thomas, C. Narayanan, D. Lakehal, and Y. Gong

ICONE21 -15345 V003T10A016

Departure From Nucleate Boiling Modeling Development for PWR Fuel

Jin Yan, L. David Smith, III, and Zeses Karoutas

ICONE21 -15480 V003T10A017

Thermal Hydraulics Numerical Simulation and Optimized Design of Passive Residual

Heat Removal Heat Exchanger in AP1000

Huining Xia, Daogang Lu, Zheng Du, Yuhao Zhang, Xiaoliang Fu, Zhongying Ma,

Yanhua Yang, and Min Liang

ICONE21 -15482 V003T10A018

Thermal Hydraulics Analysis on a Simplified Model of Spent Fuel Pool

Min Liang, Daogang Lu, Huining Xia, and Yuhao Zhang

xii

ICONE21 -15483 V003T10A019

Numerical Simulation of Self-Leveling Behavior in Debris Bed by a Hybrid Method

Liancheng Guo, Koji Morita, Hirotaka Tagami, and Yoshiharu Tobita

ICONE21 -15486 V003T1OA020

Computational Simulation of Turbulent Natural Convection in a VolumetricallyHeated Square CavityCamila Braga Vieira, Bojan Niceno, and Jian Su

ICONE21 -15606 V003T10A021

Development of PCCSAP-3D Code for Passive Containment: Models of Noncondensable Gases,

Aerosols, and Fission Products

Ran Li and Jiyang Yu

ICONE21-15644 V003T10A022

Numerical Research on Performance of AP1000 Passive Containment Cooling SystemWithout Falling Film

Hui Wang, Qiang Guo, and Qiaoyan Chen

ICONE21-15683 V003T10A023

Computational Study on a Single Flow Element in a Nuclear Thermal Rocket

Xiang Zhao, Trent Montgomery, and Sijun Zhang

ICOIME21 -15689 V003T10A024

The Effect of Electromagnetic Field on the Behavior of Bubbles

Hong-bo Liu and Liang-ming Pan

ICONE21-15735 V003T10A025

CFD Analysis of Thermal Stratification Phenomena in the RNS Suction Line of a Gen-Ill

Nuclear Power Plant

Yan Li, Daogang Lu, Zhigang Wang, Jian Wu, and Fengyun Yu

ICONE21 -15778 V003T10A026

The Research of the Fluid-Solid Interaction of the Passive Containment Cooling Tank and

Shield Building Structure With Seismic Load in AP1000

Junjie Dang, Daogang Lu, Wenhui Ma, Yu Liu, and Yang Hong

ICOIME21 -15795 V003T10A027

Study of Mixing Characteristics Over a Spacer Grid With Sloping Channels Based on Numerical

Simulations in a PWR 5x5 Rod Bundle Using CFD Codes

XI Chen and Hong Zhang

ICONE21-15818 V003T10A028

Numerical Simulation Analysis on the Flow Mechanism of Passive Containment

Cooling SystemYang Song, Wei-Hua Li, and Sheng-Qiang Li

ICONE21 -15832 V003T10A029

Numerical Investigation of Flow and Heat Transfer Characteristics in Wire-Wrap TightLattice 19-Rod Bundle

Minggang Li, Jun Wang, Changhua Nie, Xiao Yan, Yanping Huang, Zumao Yang, and

Xie Feng

xiii

ICONE21-15903 V003T10A030

Two-Way Coupling Simulation of Heat Transfer in ADS Windowless Spallation TargetJie Liu, Lei Gao, Huan Chen, Zeng-hui Wang, and Wen-qiang Lu

ICONE21-15917 V003T10A031

CFD Analysis of Circumferential Temperature Distribution of Fuel Cladding Surface of China

Lead-Alloy Cooled Research Reactor (CLEAR-I)

Zhao Chen, Guangming Zhou, Tao Zhou, Hongli Chen, and Yunqing Bai

ICONE21 -15929 V003T10A032

Study on the Flow Distribution at the Core Inlet

Mao Tang, Liang Chen, Yanwu Liu, Mingqian Zhang, and Xiaolei Yu

ICONE21 -15930 V003T10A033

Local Mesh Refinement for Viscid Flow in Combustion Code COM3D

Ke Ren, Alexei Kotchourko, and Alexander Lelyakin

ICONE21-16113 V003T10A034

Three-Dimension Thermal Hydraulic Analysis of Stationary Target Plate for Highly Intensified

Neutron Generator (HINEG)Shuzhou Li, Hongli Chen, Tao Zhou, Fengquan Song, and Wen Wang

ICONE21-16158 V003T10A035

Numerical Simulation of Supercritical Water Heat Transfer in the Vertically Heated Tube

Feng Wang, Bo Cui, Shijun Zhang, and Xue Qin

ICOIME21 -16159 V003T10A036

Full Implicit Integrate Solution to the Coupled Neutronics/Thermal-Hydraulics Problems

Han Zhang and Fu Li

ICONE21-16172 V003T10A037

Numerical Simulations and Experiments on Gaseous Flow and Heat Transfer in MultipleNarrow Channels in Transition Region

Yuming Chen, Christine Klein, Frederik Arbeiter, and German Ibaceta

ICONE21-16269 V003T10A038

Simulation of MHD Effects and Thermal Issues in the DCLL Blanket for ITER

Long Chen, Yue-Fei Du, Ming-Jiu Ni, and Nian-Mei Zhang

ICOIME21 -16290 V003T10A039

CFD Simulation of Flashing Boiling Flow in the Containment Cooling Condensers (CCC)

System of KERENA Reactor

Yixiang Liao, Dirk Lucas, Eckhard Krepper, and Roland Rzehak

ICONE21-16312 V003T10A040

Analysis of Fluid-Induced Excitation Forces in Triangular Tube Arrays Based on the LES Method

Qing-lei Jiang, Ji-yun Zhou, and Xian-yuan Wang

ICOIME21-16341 V003T10A041

Numerical Simulation on 3D Flow in the Fuel Transfer Canal and Local Flow Field AnalysisQiang Guo and Hui Wang

xiv

ICONE21-16632 V003T10A042

Predicting Thermal Mixing and Fatigue Inside Control Rod Guide Tubes

Eric Lillberg

1CONE21-16641 V003T10A043

A Numerical Simulation on Effects of Distance Between Bubble and the Wall on Behavior of

Rising Bubble

Ying Huang and Puzhen Gao

ICONE21 -16687 V003T10A044

The Modelling and Coupling Methodology of ANSYS CFX Using Porous Media for PB-AHTR

Linsen Li, Haomin Yuan, and Kan Wang

ICOIME21 -16692 V003T10A045

Multiphysics Analysis System for Tube Failure Accident in Steam Generator of

Sodium-Cooled Fast Reactor

Akihiro Uchibori, Shin Kikuchi, Akikazu Kurihara, Hirotsugu Hamada, and Hiroyuki Ohshima

ICONE21-16768 V003T10A046

Effects of Bypass Flow on the LOFA Transient Computations in a VHTR

Yu-Hsin Tung, Richard W. Johnson, Yuh-Ming Ferng, and Ching-Chang Chieng

Author Index xvii

XV