A Software Fault Tree Analysis Technique for Formal Requirement Specifications of Nuclear Reactor Protection Systems

被引:17
|
作者
Jung, Sejin [1 ]
Yoo, Junbeom [1 ]
Lee, Young-Jun [2 ]
机构
[1] Konkuk Univ, Seoul, South Korea
[2] Korea Atom Energy Res Inst, Daejeon, South Korea
基金
新加坡国家研究基金会;
关键词
Software Safety Analysis; Software Fault Tree Analysis; Requirements Specification; Formal Specification; VERIFICATION;
D O I
10.1016/j.ress.2020.107064
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Rigorous safety demonstration of software, as well as systems, is required when developing digital reactor protection systems in nuclear power plants. Various safety analysis techniques try to identify, analyze, and find remedies for potential hazards at each stage of software development life-cycle. This paper proposes a software fault tree analysis technique for software requirements written in the NuSCR formal specification language. The proposed method can mechanically construct software fault trees and calculate minimal cut-sets, encompassing timing constraints of multi-cycles, from NuSCR formal specifications. We also improved the fault tree construction and analysis tool into "NuFTA 2.0" to cope with multi-cycled executions. The case study with a preliminary version of requirements specification for a Korean nuclear power plant in operation shows the proposed technique's effectiveness and applicability to other V&Vs such as simulation.
引用
收藏
页数:20
相关论文
共 50 条
  • [1] Verifying formal specifications using fault tree analysis
    Liu, SY
    [J]. INTERNATIONAL SYMPOSIUM ON PRINCIPLES OF SOFTWARE EVOLUTION, PROCEEDINGS, 2000, : 272 - 281
  • [2] FAULT TREE ANALYSIS OF A REACTOR PROTECTION SYSTEM
    ACERO, M
    YADIGAROGLU, G
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 213 - 214
  • [3] Formal fault tree analysis of state transition systems
    Xiang, J
    Ogata, K
    Futatsugi, K
    [J]. QSIC 2005: FIFTH INTERNATIONAL CONFERENCE ON QUALITY SOFTWARE, PROCEEDINGS, 2005, : 124 - 131
  • [4] Systemic fault tolerance evaluation in nuclear reactor protection systems
    Busse, Alexander Lucas
    Losada Moreira, Joao Manoel
    Boncristiano Ozeki, Tatiana Yuri
    Gomes da Silva, Luis Geraldo
    [J]. REVISTA TECNOLOGIA E SOCIEDADE, 2020, 16 (42): : 58 - 74
  • [5] FAULT TREE ANALYSIS FOR SNAP REACTOR DISPOSAL SYSTEMS
    WILLIS, CA
    CARLSON, WJ
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (01): : 159 - &
  • [6] Research on technique of software testing based on fault tree analysis
    Ren Ying
    Lv Hong
    Li Hua-wei
    [J]. 2011 INTERNATIONAL CONFERENCE ON COMPUTER SCIENCE AND NETWORK TECHNOLOGY (ICCSNT), VOLS 1-4, 2012, : 1718 - 1720
  • [7] Software requirement analysis for digital based reactor protection system of RDE design
    Santoso, S.
    Sudarno
    Maerani, R.
    Situmorang, J.
    Cahyono, A.
    [J]. SYMPOSIUM OF EMERGING NUCLEAR TECHNOLOGY AND ENGINEERING NOVELTY (SENTEN 2018), 2019, 1198
  • [8] A formal software requirements specification method for digital nuclear plant protection systems
    Yoo, J
    Kim, T
    Cha, S
    Lee, JS
    Son, HS
    [J]. JOURNAL OF SYSTEMS AND SOFTWARE, 2005, 74 (01) : 73 - 83
  • [9] Formal Static Fault Tree Analysis
    Xiang, Jianwen
    Yanoo, Kazuo
    [J]. ICCES'2010: THE 2010 INTERNATIONAL CONFERENCE ON COMPUTER ENGINEERING & SYSTEMS, 2010, : 280 - 286
  • [10] SOFTWARE FAULT TREE ANALYSIS
    LEVESON, NG
    HARVEY, PR
    [J]. JOURNAL OF SYSTEMS AND SOFTWARE, 1983, 3 (02) : 173 - 181