摘要：
It has long been known that there are software applications for which it is difficult to detect subtle errors, faults, defects, or anomalies because there is no reliable "test oracle" to indicate what the correct output should be for arbitrary input. The absence of a test oracle clearly presents a challenge in testing the software applications of scientific computing from the domain of nuclear power plant. Metamorphic testing has been shown to be a simple yet effective technique in addressing the quality assurance of these "non-testable programs." In this paper, we introduce Metamorphic testing method to address the oracle problem as mentioned above. We identify a metamorphic relation for a real-world scientific computing programs which do not have test oracles, and demonstrate the effectiveness of metamorphic testing in identifying the error.
作者机构：
[阳小华; 闫仕宇; 刘朝晖] School of Computer Science and Technology, University of South China, Hengyang, 421001, China;[刘华; 于涛; 刘朝晖; 谢金森; 李萌; 阳小华; 闫仕宇] CNNC Key Laboratory on High Trusted Computing, Hengyang, 421001, China
通讯机构：
School of Computer Science and Technology, University of South China, Hengyang, China
作者机构：
[刘朝晖; 刘曜; 阳小华] School of Computer Science and Technology, University of South China, Hengyang;Hunan;421001, China;[陈智; 吴志强] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chendu;610041, China
作者机构：
[刘朝晖; 刘华; 阳小华] School of Computer Science and Technology, University of South China, Hengyang;421001, China;[陈智; 吴志强] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chendu;610041, China;[刘朝晖; 刘华; 阳小华] 421001, China
关键词：
STAMP模型;STPA方法;反应堆紧急停堆系统
摘要：
随着数字化技术及软件系统的广泛应用,很多事故是由于部件间异常的交互所引起,传统的分析方法已经力不从心,基于STAMP（Systems-Theoretic Accident Model and Processes）的安全性分析方法STPA（System Theoretic Process Analysis）,可以有效解决这一困难。首先介绍STPA方法及分析步骤,将该方法应用到反应堆紧急停堆子系统,得到了引起停堆失败的可能原因及设计中所应遵守的安全约束,这些约束有益于提高设计的安全性。
期刊：
International Conference on Nuclear Engineering, Proceedings, ICONE,2015年2015-January
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;[Liu, Zhaohui; Yang, Xiaohua] 421001, China
会议名称：
23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
会议时间：
17 May 2015 through 21 May 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
关键词：
Accidents;Digital control systems;Factor analysis;Hardware;Hazards;Nuclear energy;Nuclear engineering;Nuclear reactor accidents;Outages;Reconfigurable hardware;Reliability analysis;Reliability theory;Safety engineering;Safety factor;Stamping;Digital reactor protection systems;Hardware and software;Instrumentation and control;Reactor protection systems;Safety critical systems;Safety requirements;STPA;System safety;Fault tree analysis
期刊：
The Proceedings of the International Conference on Nuclear Engineering (ICONE),2015年2015.23:_ICONE23-1-_ICONE23-1 ISSN：2424-2934
作者机构：
[Zhaohui Liu; Xiaohua Yang] School of Computer Science and Technology, University of South China;[Zhiqiang Wu] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China
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-critical system, RPS in NPP needs to be considered carefully in system safety. So, we adopt this new approach to analyze the design process. From the analysis results, we found that causal factors leading to safety accidents identified by STPA included all the hazards identified by the fault tree analysis. Furthermore, there are some causal factors that were identified by STPA only. We utilize these results of the analysis on causation factor to refine the safety requirements and reduce the occurrences of the hazardous scenarios.
作者机构：
[Liu, Zhaohui; Yang, Xiaohua] School of Computer Science and Technology, University of South China, Hengyang, 421001, China;[Liao, Longtao; Wu, Zhiqiang] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China
会议名称：
23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
会议时间：
17 May 2015 through 21 May 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
关键词：
Application programs;Computer software selection and evaluation;Control systems;Cost effectiveness;Digital control systems;Failure analysis;Fault tree analysis;Hazards;Nuclear energy;Nuclear engineering;Nuclear power plants;Outages;Process control;Software design;Document evaluation;Instrumentation and control;Process control software;Regulating systems;Safety assurance;SFTA;Software fault tree analysis;Software safety analysis;Safety engineering
作者：
Zhaohui Liu;Longtao Liao;Zhiqiang Wu;Xiaohua Yang
期刊：
The Proceedings of the International Conference on Nuclear Engineering (ICONE),2015年2015.23:_ICONE23-1-_ICONE23-1
作者机构：
[Zhaohui Liu; Xiaohua Yang] School of Computer Science and Technology, University of South China;[Longtao Liao; Zhiqiang Wu] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China
作者机构：
[阳小华; 刘朝晖; 刘杰] School of Computer Science and Technology, University of South China, Hengyang, 421001, China;[陈智; 吴志强] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China
通讯机构：
School of Computer Science and Technology, University of South China, China
