Proceedings of the

18th International Conference

on Nuclear Engineering

- 2010 -

VOLUME 1

PLANT OPERATIONS, MAINTENANCE, ENGINEERING,

MODIFICATIONS, LIFE CYCLE AND BALANCE OF PLANT

FUEL CYCLE AND DECOMMISSIONING

INSTRUMENTATION AND CONTROLS

presented at

18th INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING

MAY 17-21, 2010

XI'AN, CHINA

sponsored by

NUCLEAR ENGINEERING DIVISION, ASME

THE JAPAN SOCIETY OF MECHANICAL ENGINEERS, JSME

THE CHINESE NUCLEAR SOCIETY, CNS

AS M E

Three Park Avenue New York, N.Y. 10016

CONTENTS

PLANT OPERATIONS, MAINTENANCE, ENGINEERING, MODIFICATIONS,LIFE CYCLE AND BALANCE OF PLANTICONE18-29021

1Integrated Power Recovery Using Markov ModelingShawn Rodgers, Coral Betancourt, Ernie Kee, Fatma Yilmaz, and Paul Nelson

ICONE18-290367

Life Beyond 60 Years: The Importance of Sustaining the Current Fleet of LightWater Reactors in the U. S. and the R&D Needs

Ronaldo Szilard and Hongbin Zhang

ICONE18-2904117

Root Cause Analysis of the Power Generation Capability Decrease After the 5th RefuelingOutage of Ling Ao 2

Zhiyuan Chi, Weidong Chai, Dayong Zhang, Kang Dong, Guoyun Wang, and Chun Wang

ICONE18-2904521

Codes Comparison and Analysis of Dissimilar Metal Welds:Ultrasonic Testing in Nuclear Power Plants

Zhimin Zhong, Goufeng Zhang, and Guanghua Yuan

ICONE18-2905127

Interaction of a Nuclear Power Plant With the Egyptian Electrical Grid Based on PSS/ES. Othman, H. M. Mahmoud, and S. A. Kotb

ICONE18-2909533

The Operation Characteristics of the Fuel Handling System of HTR-10Huang Peng, Xihua Liang, and Xiaoming Chen

ICONE18-29096, 41

Introduction of Interim Storage of SNF in INET

Huang Peng, Xiaoming Chen, and Lixin Jia

ICONE18-2913347

The Analysis of Effect on the Piping Due to the Displacement of EPR NuclearIsland BuildingsJunwei Wang, Zhouhong Zhang, and Gaofeng Wu

ICONE18-2913653

Commercial-Grade Item Dedication for Nuclear Safety-Related ApplicationYao-Tung Hsu and Ming-Huei Chen

ICONE18-2913959

Design, Operation and Maintenance of Thermal Hydraulic Instrumentation System ofHTR-10

Liqiang Wei and Shuoping Zhong

vii

ICONE18-29147 67

Condensate Polishing System for PWR Nuclear Power Plant

Ailing Wang

ICONE18-29155 73

Investigations and Countermeasures for Deactivation of the Hydrogen Recombination

Catalyst at Hamaoka Unit 4 and 5

Toru Kawasaki, Motohiro Aizawa, Hidehiro lizuka, Koji Yamada, and Mitsuo Kugimoto

ICONE18-29157 81

Development of Large Size Moisture Separator Reheater for Up to 1700 MW PWR Class

Issaku Fujita, Teruaki Sakata, and Toshiki Kojima

ICONE18-29194 91

Centrifugal Pump Leak-Free Technology Introduction and Its Applications in EPR

Nuclear Power Plant

Guohui Cong and Ling Zhang

ICONE18-29277 97

Life Extension of the Fast Breeder Test Reactor

B. Anandapadmanaban, A. Babu, B. Babu, K. Dinesh, V. Ramanathan, and G. Srinivasan

ICOIME18-29316 103

AP1000 Operation Procedures System and Development

Fang Wen

ICONE18-29324 109

Spread Spectrum Time Domain Reflectrometry Applied to Electrical Systems in

Nuclear Power Plants

Gary M. Sandquist and Carl J. Sandquist

ICONE18-29370 113

Development of Ultrasonic Sensor for Under-Sodium Volumetric Inspection of

Heat Exchanger PipesM. Takeishi, M. Yui, T. Kobayashi, F. Tsuri, and S. Kotake

ICONE18-29378 121

The Investigation of Classification Management for SSCS Susceptible to Ageing in PWRFei Xue, Peng Liu, Xin-ming Meng, Wen-xin Ti, Lei Lin, Zhao-xi Wang, Guo-dong Zhang,and Jia-wang Jiang

ICOIME18-29404 125

Progressive Evolution of the Core of the Fast Breeder Test ReactorS. Varatharajan, K. V. Sureshkumar, K. V. Kasiviswanathan, and G. Srinivasan

ICONE18-29424 131

Study on Integrated Method for Constructing Proactive Trouble Prevention Knowledge Base

Hidekazu Yoshikawa and Ming Yang

ICONE18-29454 137The Energy-Saving Diagnosis of PWR Nuclear Power Station Based on the Thermo-Economic

Analysis Model

Juan Chen, Tao Zhou, and Ke Ran

viii

ICONE18-29457145

Inspection of the Steam Generator Divider Plate

Filippo D'Annucci and Eric Lecour

ICONE18-29458149

Estimation of SG TSP Blockage: Innovative Monitoring Through Dynamic Behavior AnalysisMickael Midou, Julien Ninet, Alexandre Girard, and Jean-Melaine Favennec

ICONE18-29465157

Evaluation of the Conservatism of NPP Safety Analysis Dose Calculations as Typical forLicensing Purposes

Nikolaus Arnold, Nikolaus Mullner, Francesco DAuria, and Oscar Mazzantini

ICONE18-29470163

Sealing Solutions for an Aging Reactor

Timothy M. Sykes

ICONE18-29471171

Steam Generator Asset Management ProgramPadmanabha J. Prabhu and Damian A. Testa

ICONE18-29578177

Remote Field Eddy Current Testing for SG Inspection of Fast ReactorNoriyasu Kobayashi, Souichi Ueno, Satoshi Nagai, Makoto Ochiai, and Noboru Jimbo

ICONE18-29591183

State Oriented Procedure Application in Nuclear Power Plants in ChinaQingming Yang

ICONE18-29608187

Advances and Research Needs in Risk-Informed In-Service Inspection MethodologyX.-X. Yuan

ICONE18-29615195

Evaluation on Radiological Consequence Induced by MSLB Accident WithAlternative Source Term

Jingxi Li, Gaofeng Huang, and Lili Tong

ICONE18-29656201

The Mass Concrete Construction Methodology Exploring and Practice for Ensuring QualityApplied in the First AP1000 Project

Xiao Liu

ICONE18-29700207

Maintenance Strategy for Branch Connection on the Hot Leg of Steam Generator inCANDU 6

Liang Zhao, Jianqun Hu, Zhigang Wu, and Xin Wang

ICONE18-29701213

Improvement of Flange Tightening Method for Small Bore Low Rating Bolted FlangesMasako Mori, Akira Nebu, and Takashi Kanno

ix

ICONE18-29702 223

Digital Image Evaluation Method for Digital RadiographyMasako Mori, Toshibumi Kashiwa, and Yoshimitsu Aoki

ICONE18-29703 229

Performance Evaluation of Japanese Nuclear Power Plant Based on Open Data and

Information (3)Tadahisa Nagata and Ken-ichiro Sugiyama

ICONE18-29733 235

BWR Recirculation Pump Adjustable Speed Drive Performance and Control Affects

James W. Morgan and Timothy Gode

ICONE18-29738 243

Management of Single Point Vulnerability Components

Yijun Yu, Ligen Xu, Xin Wang, and Liansheng Wang

ICONE18-29746 251

LOCA Event Tree Analysis for Qinshan Phase III CANDU-6 PHWR NPP

Limin Zheng

ICONE18-29802 261

Optimization of Production Plan and Risk Control in Qinshan III NPP

Jun Zhou

ICONE18-29803 267

Building Effective Organizations and Measures to Cope With Severe Weather in

Qinshan III NPP

Jun Zhou

ICONE18-29812.... 273

Modeling of NPP Canned Motor Pump Performance Degradation Assessment Based on

Multi-Agent SystemZhang Liming

ICONE18-29826 279

Dynamic Behavior of Cracked Cantilevered Pipes Conveying Fluid

Fengchun Cai, Fenggang Zang, and Xianhui Ye

ICONE18-29843 289

Crack Growth Monitoring by Strain Measurement of the External Surface of Cracked Pipes:A Feasibility Study

Masayuki Kamaya and Koj'i Miyoshi

ICONE18-29845 295

The Outline of the Five-Percent Power Uprate Project in Tokai-2

Hitoshi Ohata, Toshikazu Nishibata, and Tetsuya Onose

ICOIUE18-29894 301

Dr. Mainte: An Integrated Simulator for Optimization of Maintenance Strategies of

Light Water Reactors

Yoshihiro Isobe and Mitsuyuki Sagisaka

x

ICONE18-30033 305

Development of Remotely Operated Inspection Devices for BWR Internals

Mitsuaki Shimamura, Yutaka Togasawa, Hisashi Hozumi, Naruhiko Mukai, and

Yasuhiro Yuguchi

ICOIME18-30057 311

TRACE5 Simulation of Condensation-Induced Water Hammer Phenomena

S. Gallardo, V. Abella, and G. Verdu

ICONE18-30150 319

Management and Practice of CPR1000 Nuclear Power Plants: Commissioning and StartupYu Yang and Wang Can

ICONE18-30238 325

Investigation on Integrity of JMTR Reactor Pressure Vessel

Hiroshi Ide, Akihiro Kimura, Hiroshi Miura, Yoshiharu Nagao, Naohiko Hori, and

Masanori Kaminaga

ICONE18-30240 335

Snapshot Review of the Regulation of Gas Voids in Nuclear Steam Supply Systems in the

United States

L Ike Ezekoye and William M. Turkowski

ICONE18-30261 345

An Analytical Method for Modeling Two-Phase Gravity-Driven Drainage Systems in

BOP ApplicationsRobert Stakenborghs and Michael L. Morgan, Jr.

ICONE18-30281 355

The Development of SRCM and the Application at Home and Abroad

Lifei Yang and Jiang Hong

ICONE18-30291 361

Execution of 18 Month Refueling Modification and Experience Feedback

Guo-long Sheng and Yang Pu

ICONE18-30329 367

A Procedure to Address the Fuel Rod Failures During LB-LOCA Transient in Atucha-2 NPP

Martina Adorni, Alessandro Del Nevo, Francesco D'auria, and Oscar Mazzantini

ICONE18-30355 377

The Advanced Installation Method of Containment Liner Plates

Woosung Kim and Jihong Park

FUEL CYCLE AND DECOMMISSIONING

ICONE18-29006 383

New Composite Materials for Decreasing of Radioactive Molecular Iodine in the

Water Coolant on the Working and New Developed NPPSS. A. Kulyukhin, L. V. Mizina, and A. A. Tishina

xi

ICONE18-29028 387

Application of Formohydroxamic Acid in Nuclear Processing: Synthesis and ComplexationWith Technetium-99

Patricia Paviet-Hartmann, Amber Wright, Edward Mausolf, Keri Campbell, and

Frederic Poineau

ICONE18-29057 393

Researches on the In-Core Reload Design for TianWan Nuclear Power Station

Hongxia Wang

ICONE18-29058 399

Simulation and Analysis: The Dose Distribution of KBS-3 Spent Nuclear Fuel Canister

by MCNPBo Yang, He-xi Wu, and Yi-bao Liu

ICONE18-29066 405

Acid Stimulation Used in In-Situ Leaching Uranium

Wen-sheng Liao, Li-min Wang, Yi-xuan Yao, Guo-ping Jiang, Hahjun Zhao, and

Xin Huang

ICONE18-29075 413

The Implementation of Radiological Characterization for Reactor DecommissioningJunxian Deng, Huasong Zhao, Xin Li, and Feng Deng

ICONE18-29091 419

Selective Separation and Recovery of Cesium by Ammonium Tungstophosphate-Alginate

MicrocapsulesHitoshi Mimura, Yan Wu, Yufei Wang, Yuichi Niibori, Isao Yamagishi, Masaki Ozawa,

Takashi Ohnishi, and Shinichi Koyama

ICOIME18-29098 429

Testing of Transuranus Code for RIA Analysis: The FK-1 NSRR Case

R. Calabrese and F. Vettraino

ICONE18-29300 437

Burn-Up Calibration and Error Analysis of HTR-10 Spherical Fuel Elements byGamma Spectroscopy

Bing Xia, Fu Li, and Zongxin Wu

ICONE18-29358 445

N,N,N',N'-Tetra-Methyl-3-Oxy-Pentane-1,5-Diamide (TMPDA): A Promising Back Extractantfor Ln(lll) and Zr(IV)

Meng Wei, Qian'ge He, Xuegang Liu, and Jing Chen

ICONE18-29436 451

FCC-NG: The AREVA Safe Fresh Fuel Shipping Cask to Deliver the Future EPR ReactorsM. Doucet, P. Faye, Ch. Faignet, R. Babut, M. Landrieu, F. Marvaud, and G. Romanet

ICONE18-29574 457Nuclear Fuel Cycle: Which Strategy to Sustain Nuclear Renaissance?

Renaud Liberge and Marc Arslan

xii

ICONE18-29632 465

The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle

Guang Jun Chen, Yu Lin Cui, Guo Guo Zhang, and Hong Jun Yao

ICONE18-29751 469

Synthesis of Results Obtained With Laser Cutting, a Promising Dismantling Tool

Guy Pilot

ICONE18-29875 477

Transport of MOX Fuel: A Continuous ChallengeAnnabel Potot

ICONE18-29889 ,483

Poolside Examination Techniques Applied for Development of an Advanced

PWR Fuel, PLUS7

Jung-Cheol Shin, Jae-lk Kim, and Jung-Tack Kwon

ICONE18-29914 489

Extraction of Actinides and Lanthanides by Supercritical Fluid

Liyang Zhu, Wuhua Duan, Jingming Xu, and Yongjun Zhu

ICONE18-29985 501

Treatment and Disposal of the Radioactive Graphite Waste

Lifang Tian, Mingfen Wen, and Jing Chen

ICONE18-30008 511

Development of Integrated Treatment System to Minimize LLLW From a PUREX

Reprocessing Plant

Yasuhiro Suzuki, Mitsuaki Kumazawa, Shekar Balagopal, Yasutomi Morimoto,

Hikarai Egami, Takashi Kato, and Mamoru Numata

ICOINIE18-30041 517

Discussion of the Effects of AP1000 First Core Loading Pattern Design on Nuclear

Power Plant Operation

Xuesong Li

ICONE18-30092 523

Radioactive Waste Water Treatment by Inorganic Membrane System

Junfeng Li, Fujuan Han, and Jianlong Wang

ICONE18 30110 529

Based on 200L Barrels of Low-Level Solid Waste Encapsulates Device DesignAiguo Shang, Jin Qin, and Changjie Lu

ICONE18-30123 533

Scenarios for the Transmutation of Actinides in CANDU Reactors

Bronwyn Hyland and Brian Gihm

ICONE18-30137,

545

The Study on Pyrolytic Carbon Powder in the Coating Process of Fuel Particle for

High-Temperature Gas-Cooled Reactor

Malin Liu, Bing Liu, and Youiin Shao

xiii

IC0NE18-30141 551

Development of Superfine Spherical Silica Grout as an Alternative Grouting Material for the

Geological Disposal of Long-Lived Radioactive Waste

Morimasa Naito, Hirokazu Kishi, Naomi Fukuoka, Tsutomu Yamada, and Hideaki Ishida

ICONE18-30154 559

Efficiency of Sulfoaluminate Cement for Solidification of Simulated Radioactive

Borate Liquid WasteQina Sun, Junfeng Li, Jianlong Wang, Shixi Ouyang, Qiang Li, and Minghui Wu

ICOIME18-30164 565

The Application of Uniform Design Table in Cement Solidification of Nuclear Waste Resin

Minghui Wu, Qiang Li, and Shixi Ouyang

IC0NE18-30166 571

Study on Applicability of Simple Conversion Factor for In-Situ Activity Measurement

Yuko Onishi, Satoru Kawasaki, and Masami Kato

ICOIME18-30227 577

Recent GEH Criticality Safety Activities in Support of the Nuclear Fuel CycleLon Paulson, John Zino, and Qi Ao

ICOIME18-30336 581

Plutonium Rock-Like Oxide Fuel (ROXF) System: Their Once-Through Burning and UsageAshraf Elsayed Mohamed Mohamed

INSTRUMENTATION AND CONTROL (l&C)ICONE18-29001 585

Core Protection Calculator System: Past, Present and Future

Pefer L. Hung

ICONE18-29011 593

Study on Technical Improvements for Human System Interface in the Main Control Roomof LINGAO 3&4

Shi Ji, Xiaomei Xu, Jianbo Zhang, and Zhifang Wang

ICONE18-29029 599The Application of FPGA for Anticipated Transients Without Scram Mitigation System

Mao-Sheng Tseng, Hui-Wen Huang, Ming-Huei Chen, Tsung-Chieh Cheng,Hsiang-Han Chung, Tzeng-Hsi Liu, Wen-Lung Yang, Ming-Chung Lee, and

Mao-Yuan Chen

ICONE18-29055 611A Nodal Dynamic Model for Control System Simulation of the HTR-PM Reactor CoreZhe Dong, Xiaojin Huang, and Liangju Zhang

ICONE18-29056 619

Output-Feedback Load-Following Control of Nuclear Reactors Based on a DissipativeHigh Gain Filter

Zhe Dong, Xiaojin Huang, and Liangju Zhang

xiv

IC0NE18-29089 627

Study of Unique Foam Detecting Sensor

Shengqiang Li, Shengyao Jiang, Shuoping Zhong, Wenran Wang, and Hanliang Bo

ICONE18-29102 635

Developing Software Configuration Management System for Digital Instrumentation and

Control (DI&C) System of Nuclear Power Plant

l-Hsin Chou, Hsueh-Wei Hsiao, and Che-An Chang

ICONE18-29224 641

Simulation and Realization of Nuclear Instrument SystemGuangxia Zuo, Bin He, Wenyan Ma, Xiaolin Qiu, and Weihua Hui

ICONE18-29230 645

An Open-Walled Ionization Chamber Appropriate to Tritium Monitoring for Glovebox

Zhilin Chen and Heyi Wang

ICONE18-29232 651

Study and Design of Monitoring System of Reactor Coolant Pump in Nuclear Power Plant

You Lei, Fuchun Sun, Pan He, Hongkun Xu, and Fang Fang

ICONE18-29264 659

Effective Software Verification and Validation Approach for Nuclear Power Plant DigitalInstrumentation and Control Systems

Steve Yang, Jun Ding, Huifang Miao, and Jianxiang Zheng

ICONE18-29286 667

Test Facility Design for Integrated Digital Nuclear Reactor Protection System

Huasheng Xiong, Duo Li, and Liangju Zhang

ICONE18-29305 673

Design of an Ethernet Bus Interface Controller in a Nuclear Power Plant Simulator

Lixuan Lu and Dong Le

ICONE18-29310 679

An Investigation on the Minimum Inventory of Human System Interfaces for

Plant's Safe OperationChih-Wei Yang, Tzu-Chung Yenn, Tsung-Chieh Cheng, Ming-Huei Chen, and

Tung-Ming Wu

ICONE18-29396 685

The Development of a Generic Qualified Digital Platform

S. S. Shyu Victor and Ming-Huei Chen

ICONE18-29487 691

Full Digital l&C System in Tianwan Nuclear Power Station: Summary of OperationalExperience and Analysis of Typical Events

Qingwei Shi and Ping Zhou

ICONE18-29500 701

Design of Remote Control System for Far-Infrared Laser Interferometer

Nan Shi, Xiang Gao, Yinxian die, Erhui Wang, and Yao Yang

xv

ICONE18-29510 707

A Study on Fault Diagnosis Technology of Nuclear Power Plant Based on Decision Tree

Yu Mu and Hong Xia

ICOWE18-29512 711

The Design and Simulation of Voltage-Preamplifier With Numerical-Controlled Plus

Wenyan Ma, Guojian Yu, and Jian Chang

IC0NE18-29556 715

Human Factors Engineering Verification and Validation: A Case Study of a

Nuclear Power Plant

Fei Song and Shuhui Zhang

ICONE18-29587 723

Study on a Methodology of Human Factor Engineering Operating Experience Review for

Nuclear Power Plant

Danying Gu, Shuhui Zhang, and Zhonghe Ning

ICONE18-29589 731

Design of Wireless Heterogeneous Framework for Radiation Monitoring in

Nuclear Power Plant

Shouwei Gao, Danying Gu, Weidong Zhang, and Xiaojin Zhu

ICONE18-29596 737

A Study on Human Reliability About Human Machine Interface in Accident Situation of

Nuclear Power Plant

Pengfei Gu, Zhifang Wang, and Jianbo Zhang

ICONE18-29600 743

A Study About Human Workload Forecasting Method of Nuclear Power Plant

Guojin Jiang, Pengfei Gu, and Yongbin Sun

ICONE18-29603 749

A Study on Evaluation Method About Human-Machine System Interface for

Nuclear Power Plant

Yongbin Sun, Pengfei Gu, and Guojin Jiang

ICONE18-29754 755

Diversity-Oriented FPGA-Based NPP l&C Systems: Safety Assessment, Development,Implementation

Vyacheslav S. Kharchenko, Eugenii S. Bakhmach, AlexandrA. Siora, Vladimir V. Sklyarand Viktor I. Tokarev

ICONE18-29777 765Fault Detection and Identification in NPP Instruments Using Kernel PrincipalComponent Analysis

Jianping Ma and Jin Jiang

ICONE18-29779 773Candu Reactor Space-Time Kinetic Modeling for Load Following Control

Lingzhi Xia and Jin Jiang

xvi

IC0NE18-29799 783

New Human-Machine Interface at VR-1 Training Reactor

Martin Kropik, Jan Rataj, and Monika Junckova

ICONE18-29820 793

Adaptive Unbalance Vibration Control of Active Magnetic Bearing Systemsfor the HTR-10GT

Chao Hui, Lei Shi, Jie Wang, and Suyuan Yu

ICONE18-29922 803

A Convenient Multi-Model Simulation Technique for Nuclear Reactor SystemJinfeng Peng, Fuyu Zhao, and Cheng Liu

ICOIME18-29928 809

US-APWR Human System Interface System Verification and Validation Program for

Digital l&C DesignSatoshi Hanada, Koji Ito, and Kenji Mashio

ICONE18-29958 815

Development of a Test Facility and Its Application for Validation and Reliability Testing of

Safety-Critical Software

M. Zhao and N. Tailor

ICOIME18-30055 821

Development of Nuclear-Specific Coriolis Flowmeters Based on the

Straight-Tube TechnologyTao Wang and Yousif Hussain

ICONE18 30074 827

Mitsubishi Digital l&C Design Features for PWR Plant

Shunsuke Ishimoto, Hirokazu Fumon, and Masanori Yokoyama

ICONE18-30095 835

Study of the Characteristic Response of Pressure Control System in Order to Obtain the

Design Parameters of the New Control System MARK VI Turbine in Cofrentes

Nuclear Power Plant

Laura Bucho, Maria Jose Palomo, Juan Ignacio Vaquer, Belen Lopez, Gregorio Ruiz,

Jose Antonio Mora, and Gumersindo Verdu

ICONE18-30099 841

Applying Markov Processes for KIC Minimum Configuration Calculation

Ke Tan, Guojin Jiang, Yongbin Sun, Huaqing Peng, and Shi Ji

ICONE18-30183 845

The Incorporation of Task Analysis Into AP1000 Control Rooms DesignJulie Reed, Ruiqi Ma, and Zhonghai Li

ICONE18-30186 851

Research and Application of Safety Information and Control System of Nuclear

Power Station

Liming Zhang, Weijun Huang, Yongbin Sun, and Guojin Jiang

xvii

ICOISIE18-30236 855

The Summarization of Power Coordinated Control of Reactor and Turbine

Xiaosheng Dong, Xiafeng Li, Guangming Liu, Yajie Tian, Guobin Xu, Weijun Huang, and

Guojin Jiang

ICONE18-30237 861

Reactor Protection Diversity Requirements and the Typical Solution Base on DCS

Wei-Jun Huang, Ya-Jie Tian, Xiao-Sheng Dong, Li ming Zhang, Guang-Ming Liu, and

Guo-Jin Jiang

ICONE18-30239 867

Measurement of Gamma Radiation Profile Inside a Candu® Reactor

S. Yue, B. H. Smith, G. Jonkmans, B. Sur, D. Comeau, and D. Taylor

ICONE18-30278 873

Current Trends in l&C Diversity ImplementationC. Daniel Stiffler and Stephen Seaman

ICOIME18-30317 877

Condition Assessment of NPP Cables Through Indenter Modulus and Break-Elongation Test

Tao Liu, Han Fei, Haining Shi, and Xinming Jin

ICONE18-30320 883

Safety System and Control System Separation Requirements for ACR-1000 and

Operating CANDU® Reactors

Sun/7 Tikku, Gilbert Raiskums, John Harber, and Phil Foster

ICONE18-30323 893

Calibration of Activation Counter by a 2.48 kJ Plasma Focus Device

Sahar Rajabi Moghadam, Fereydoon Abbasi Davani, and Babak Shirani Bidabadi

ICONE18-30345 897

Integrating Cyber Security Into Nuclear Digital l&C Safety SystemsDeanna Jing Zhang

ICONE18-30358 903

Digital Instrumentation and Control Systems Upgrades in Current Generation

Nuclear Power Plants

Steven A. Arndt

ICONE18-30366 911

Research on Distribute Real-Time Database Based on Vxworks

Huwei Li, Duo Li, and Huasheng Xiong

ICONE18-30369 915RCCE-E 2005: Creator of Confidence Between Nuclear Safety Authority, Owner and Suppliers

J. M. Haure

ICONE18-30373 921Research on Digital Nuclear Power Measurement EquipmentDuo Li, Huasheng Xiong, and Liangju Zhang

Author fndex

xviii

925