Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems: The Second International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant

266 Pages·2018·21.82 MB·English

by  Yang Xu

Lecture Notes in Electrical Engineering 455
Yang Xu
Feng Gao
Weihua Chen
Zheming Liu
Pengfei Gu Editors
Nuclear Power Plants:
Innovative Technologies
for Instrumentation
and Control Systems
The Second International Symposium
on Software Reliability, Industrial Safety,
Cyber Security and Physical Protection
of Nuclear Power Plant
Lecture Notes in Electrical Engineering
Volume 455
Board of Series editors
Leopoldo Angrisani, Napoli, Italy
Marco Arteaga, Coyoacán, México
Samarjit Chakraborty, München, Germany
Jiming Chen, Hangzhou, P.R. China
Tan Kay Chen, Singapore, Singapore
Rüdiger Dillmann, Karlsruhe, Germany
Haibin Duan, Beijing, China
Gianluigi Ferrari, Parma, Italy
Manuel Ferre, Madrid, Spain
Sandra Hirche, München, Germany
Faryar Jabbari, Irvine, USA
Janusz Kacprzyk, Warsaw, Poland
Alaa Khamis, New Cairo City, Egypt
Torsten Kroeger, Stanford, USA
Tan Cher Ming, Singapore, Singapore
Wolfgang Minker, Ulm, Germany
Pradeep Misra, Dayton, USA
Sebastian Möller, Berlin, Germany
Subhas Mukhopadyay, Palmerston, New Zealand
Cun-Zheng Ning, Tempe, USA
Toyoaki Nishida, Sakyo-ku, Japan
Bijaya Ketan Panigrahi, New Delhi, India
Federica Pascucci, Roma, Italy
Tariq Samad, Minneapolis, USA
Gan Woon Seng, Nanyang Avenue, Singapore
Germano Veiga, Porto, Portugal
Haitao Wu, Beijing, China
Junjie James Zhang, Charlotte, USA
About this Series
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Yang Xu Feng Gao Weihua Chen
(cid:129) (cid:129)
Zheming Liu Pengfei Gu
(cid:129)
Editors
Nuclear Power Plants:
Innovative Technologies
for Instrumentation
and Control Systems
The Second International Symposium
on Software Reliability, Industrial Safety,
Cyber Security and Physical Protection
of Nuclear Power Plant
123
Editors
Yang Xu ZhemingLiu
Department ofEngineering Physics ProductInformation Committee
TsinghuaUniversity ofChina InstrumentandControl Society
Beijing Beijing
China China
FengGao PengfeiGu
ChinaNuclear Power Design Co.,Ltd. ChinaNuclear Power Design Co.,Ltd.
Shenzhen,Guangdong Shenzhen,Guangdong
China China
WeihuaChen
ChinaNuclear Power Design Co.,Ltd.
Shenzhen,Guangdong
China
ISSN 1876-1100 ISSN 1876-1119 (electronic)
Lecture Notesin Electrical Engineering
ISBN978-981-10-7415-8 ISBN978-981-10-7416-5 (eBook)
https://doi.org/10.1007/978-981-10-7416-5
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Preface
The Second International Symposium on Software Reliability, Industrial Safety,
Cyber Security and Physical Protection of Nuclear Power Plant (ISNPP) was
successfully held in Chengdu, China, from August 23 to 25, 2017.
We are very pleased to see that since last year’s symposium, the academic
exchange has been promoted among the participants on every aspects of nuclear
powerplants’instrumentationandcontrol system.Thissymposiumhasbecomean
effective platform for nuclear power builders, regulators, research institutions, and
manufacturers. At the same time, a number of outstanding independent research
results and products were implemented, such as the speed monitoring device for
1E-class main pump, the verification and validation for security level and the
commercial grade software. In fact, many issues discussed in the symposium
provide a lot of important reference and strong support for the related work of
nuclear power plant.
120 researchers, experts, and students from 29 units attended this symposium,
including Tsinghua University, the Ministry of Environmental Protection, China
NuclearSociety,andtheChinaGeneralNuclearPowerGroup.Wereceivedatotal
of 76 papers; after anonymous peer review and expert selection, 30 outstanding
papers were finally recommended to LNEE published, including 9 remarked
excellent papers. We hope these papers could also provide beneficial help for the
entire instrumentation and control system industry.
On the occasion of the publication of these papers, we would like to thank the
organizers of the symposium for providing a good platform for the majority of
nuclear power practitioners, also very grateful thanks to the experts and scholars
whoprovidereviewandguidanceforthepaper.Finally,weextendappreciationto
the authors of the relevant papers, and it is their constant study and efforts to the
sophisticated technology that makes it possible to publish this volume of papers
successfully.
v
Organization
Editor and Organizing Committee
Xu Yang Department of Engineering Physics, Tsinghua University
Beijing, China
Gao Feng China Nuclear Power Design Co., Ltd., China
Chen Weihua China Nuclear Power Design Co., Ltd., China
Liu Zheming Product Information Committee of China Instrument
and Control Society, China
Gu Pengfei China Nuclear Power Design Co., Ltd., China
Executive Committee
Chen Yanfeng Product Information Committee of China Instrument
and Control Society, China
Yu Yuzhou Product Information Committee of China Instrument
and Control Society, China
vii
Contents
A Design of High Efficient Multipoint Communication Systems
in Nuclear Safety Digital Control Systems . . . . . . . . . . . . . . . . . . . . . . . 1
Guo-Jin Jiang, Le Li, Gui-Lian Shi, and Yong Zhao
A Study and Application About Software V&V Requirement
Management Scheme in Digital RPS . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
Wang Xi, Peng-Fei Gu, Wei Liu, and Wei-Hua Chen
The Software Security Analysis for Digital Instrumentation
and Control Systems of NPPs. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21
Hui-Hui Liang, Peng-Fei Gu, Jian-Zhong Tang, and Wei-Hua Chen
Application of Variable Frequency Control Technology
in Solid Waste Treatment System of Nuclear Power Plant. . . . . . . . . . . 27
Jing-Jie Bo, Li Zhou, and Cong Xue
Application Research of the Computer-Based Post-Accident
Monitoring System on the Third Generation Nuclear Power Plant . . . . 33
Xiang-Jie He
Study About UI Design Optimization of TNPS MMI. . . . . . . . . . . . . . . 42
Jie Xu
Study on I&C Safety Classification Method of Nuclear Power Plant . . . 50
Tao Fu, Xiang-Jie He, and Long-Qiang Zhang
The Optimization of Valve Control Strategy for Valve Periodic
Test in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58
Xiao-Lei Zhan, Yan Liu, and Bin Zeng
Transient Detection and Identification for HTR-PM Based
on Principle Component Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 65
Shu-Qiao Zhou, Chao Guo, and Xiao-Jin Huang
ix
x Contents
Research on Test for Spray/Immersion Conditions with Extreme pH
of Third Generation Nuclear Class 1E Cables . . . . . . . . . . . . . . . . . . . . 73
Xin-Yu Wang, Fei-Fei Zhu, Qi Wu, and Jing-Yuan Yang
The Selection of Neutral Grounding Method for Stationary Medium
Voltage Power Supply System in Nuclear Power Plant . . . . . . . . . . . . . 85
Jing Kong, Qi Zhang, Da-Hu Liu, Peng Liu, Yan Feng, and Zi-Xi Chen
Discussion on Application of FPGA Technology in Safety
Instrument and Control System of Nuclear Power Plant . . . . . . . . . . . . 94
Jing-Yuan Yang, Qi Wu, Xin-Yu Wang, and Shao-Hua Han
Research of Critical Reactivity Control Online Early Warning
Technology in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . 102
Hong-Yun Xie, Ji-Xue Li, Zhen-Yu Yan, and Ke Tan
Analysis and Optimization of Layout Solution of Instrumentation
and Control (I&C) Cable Channel for Digital NPP . . . . . . . . . . . . . . . . 109
Ying Meng, Nian-Wu Lan, Tian Deng, and Li-Ping Zhong
Research and Comparison of Combination Control Schemes Between
Reactor and Turbine in Different PWR Nuclear Power Plant . . . . . . . . 115
Xu-Feng Wang and Le-Yuan Bai
Study on Three-Dimensional Virtual Visualization
Monitoring Method and System of Real-Time Information
in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 123
Jing Zeng, Tian-Nan Yang, Zhen-Yu Yan, and Zhi-Yong Li
The Overview in Safety Review of Human Factors
Engineering and Control Room Design in Chinese AP1000
Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 131
Yan Feng, Zhong-Qiu Wang, Qi Wu, Yun-Bo Zhang, and Jing-Bin Liu
Risk Analysis of Cyber Security in Nuclear Power Plant. . . . . . . . . . . . 139
Zhen-Yu Yan, Zeng-Jun Chun, Gao-Jun Liu, and Lai-Long Zou
Commercial Grade Dedication for Software Life Cycle
of Digital Instrument and Control Equipment . . . . . . . . . . . . . . . . . . . . 148
Qi Wu, Yun-Bo Zhang, Shi-Xin Li, and Xin-Yu Wang
Electric Isolation Test Research and Application of Safety Class
Equipment Qualification in Nuclear Power Plants . . . . . . . . . . . . . . . . . 156
Zhong-Qi Liang, Hua-Ming Zou, Hong-Wei Pei, Guo-Jin Jiang,
and Chun-Ming Liu
The Appliance of BOP Auxiliary System Centralized Control
Network in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 167
Lei Jiang
Contents xi
Research on New Displacement Sensor Used in Active Magnetic
Bearing Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 174
Lian-Xiao Xue, Kai Zhang, and Yang Xu
The R&D of FPGA-Based FitRel Platform in Nuclear Power
Plant Diversity Actuation System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 188
Yong-Bin Sun, Chun-Lei Zhang, Yin-Jie Chen, and Tao Bai
Overview of Development of NPP Advanced Main Control
Room Console . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 196
Qing-Jun Meng, Zhi-Bin Liu, and Yong-Bin Sun
Implementation of V&V Tasks for Improving Nuclear I&C
System Software Safety . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 206
Bao-Juan Yin, Jing Li, Ya-Qi Wang, Da-Hu Liu, and You-Yuan Li
Feasibility Analysis and Application Principle of Field Bus
Technology in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . 215
Wei Sun, Jin-Na Ma, Chu-Hao Xi, and Long-Qiang Zhang
The Analysis of Periodic Test Solution for Main Feedwater
Isolation Valve . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 225
Zhi-Hong Lv
Evaluation Measures About Software V&V of the Safety
Digital I&C System in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . 233
Peng-Fei Gu, Zhe-Ming Liu, Hui-Hui Liang, Wei-Hua Chen,
and Feng Gao
Software Requirement Evaluation Method for Safety I&C
System of Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 240
Jian-Zhong Tang, Peng-Fei Gu, Sheng-Chao Wang, Ya-Nan He,
and Wei-Hua Chen
Discussion on Multi-dimensional Security System of See-Air-Land
in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 248
Shuang Li, Wei-Dong Liu, Zhe-Ming Liu, Peng-Fei Gu,
and Wei-Hua Chen
Author Index.. .... .... .... ..... .... .... .... .... .... ..... .... 255