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Application of STPA to the digital reactor protection system in NPP for system safety analysis

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成果类型:
期刊论文、会议论文
作者:
Liu, Zhaohui;Wu, Zhiqiang;Yang, Xiaohua
作者机构:
[Liu, Zhaohui; Yang, Xiaohua] School of Computer Science and Technology, University of South China, Hengyang, 421001, China
[Wu, Zhiqiang] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China
语种:
英文
关键词:
Digitalized instrumentation and control;Reactor Protection system;STAMP;STPA;System safety analysis
期刊:
International Conference on Nuclear Engineering, Proceedings, ICONE
年:
2015
卷:
2015-January
会议名称:
23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
会议时间:
May 17, 2015 - May 21, 2015
会议地点:
Chiba, Japan
会议主办单位:
(1) School of Computer Science and Technology, University of South China, Hengyang; 421001, China; (2) Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu; 610041, China
会议赞助商:
et al.;GLSEQ, LLC/SCI Technologies. Inc;Hitachi-GE Nuclear Energy, Ltd.;Mitsubishi Heavy Industries, Ltd. (MHI);Toshiba Corporation;Westinghouse Electric Company
出版者:
American Society of Mechanical Engineers (ASME)
机构署名:
本校为第一机构
院系归属:
计算机科学与技术学院
摘要:
In NPP, the digital control system which integrated software and hardware are increasingly used to improve dependability and introduce new functionality. Traditional safety analysis can get a good result when handling accidents caused by component failures, but software does not fail in this way. STPA is a new hazard analysis technique based on systems theory rather than reliability theory. It considers the system as a whole (include the hardware and software) to analyze failure and causality of systems and treats safety as a control problem rather than a failure problem. Being a safety-critic...

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