The software V&V tasks for a safety-critical software based protection system in nuclear power plants

被引:0
|
作者
Cheon, S. W. [1 ]
Park, G. Y. [1 ]
Cha, K. H. [1 ]
Lee, J. S. [1 ]
Kwon, K. C. [1 ]
机构
[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea
关键词
D O I
暂无
中图分类号
TP39 [计算机的应用];
学科分类号
081203 ; 0835 ;
摘要
This paper introduces the software life-cycle based V&V (verification and validation) tasks for the KNICS (Korea nuclear instrumentation and control system) project. The objectives of the V&V tasks are mainly to develop the programmable logic controller (PLC) for safety-critical instrumentation and control (I&C) systems, and then to apply the PLC to developing the prototype of the safety-critical software based digital protection system in nuclear power plants. As preparative works for the software V&V, various kinds of software plans and V&V task procedures have been developed according to a software life-cycle management. A number of software V&V tools have been adopted or developed to support the V&V tasks. The V&V techniques employed in this work include a checklist-based review and inspection, the requirement traceability analysis, a formal specification and verification, a lifecycle based software testing, a software safety analysis, and a software configuration management.
引用
收藏
页码:366 / 371
页数:6
相关论文
共 50 条
  • [1] Implementation of V&V Tasks for Improving Nuclear I&C System Software Safety
    Yin, Bao-Juan
    Li, Jing
    Wang, Ya-Qi
    Liu, Da-Hu
    Li, You-Yuan
    NUCLEAR POWER PLANTS: INNOVATIVE TECHNOLOGIES FOR INSTRUMENTATION AND CONTROL SYSTEMS, 2018, 455 : 206 - 214
  • [2] A Study of Implementation V&V Activities for Safety Software in the Nuclear Power Plant
    Liang, Hui-hui
    Gu, Peng-fei
    Tang, Jian-zhong
    Chen, Wei-hua
    NUCLEAR POWER PLANTS: INNOVATIVE TECHNOLOGIES FOR INSTRUMENTATION AND CONTROL SYSTEMS, 2017, 400 : 23 - 31
  • [3] V&V-based remaining fault estimation model for safety-critical software of a nuclear power plant
    Eom, Heung-seop
    Park, Gee-yong
    Jang, Seung-cheol
    Son, Han Seong
    Kang, Hyun Gook
    ANNALS OF NUCLEAR ENERGY, 2013, 51 : 38 - 49
  • [4] Software V&V methods for safety digital I&C system of nuclear power plant
    Ye, Wang-Ping
    Tang, Jian-Zhong
    Chen, Wei-Hua
    Gu, Peng-Fei
    Wang, Sheng-Chao
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2015, 49 : 377 - 381
  • [5] ASSESSMENT OF SAFETY-CRITICAL SOFTWARE IN NUCLEAR-POWER-PLANTS
    PARNAS, DL
    ASMIS, GJK
    MADEY, J
    NUCLEAR SAFETY, 1991, 32 (02): : 189 - 198
  • [6] A STUDY ABOUT SAFETY I&C SYSTEM SOFTWARE V&V IN NUCLEAR POWER PLANT
    Gu, Pengfei
    Wang, Shengchao
    Chen, Weihua
    Yu, Suyuan
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 1, 2016,
  • [7] Software V&V methods for digital plant protection system
    Kim, HJ
    Han, JB
    Chun, CS
    Kim, S
    Kim, KJ
    PROCEEDINGS OF THE INTERNATIONAL TOPICAL MEETING ON ADVANCED REACTORS SAFETY, VOLS 1 AND 2, 1997, : 796 - 801
  • [8] Safety analysis of safety-critical software for nuclear digital protection system
    Park, Gee-Yong
    Lee, Jang-Soo
    Cheon, Se-Woo
    Kwon, Kee-Choon
    Jee, Eunkyoung
    Koh, Kwang Yong
    COMPUTER SAFETY, RELIABILITY, AND SECURITY, PROCEEDINGS, 2007, 4680 : 148 - +
  • [9] TECHNICAL ARCHITECTURE ABOUT SAFETY I&C SYSTEM SOFTWARE V&V IN NUCLEAR POWER PLANT
    Wang, Shengchao
    Gu, Pengfei
    Ye, Wangping
    Chen, Weihua
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 1, 2017,
  • [10] Evaluation System of Software Concept V&V About the Safety Digital I&C System in Nuclear Power Plant
    Gu, Peng-Fei
    Xi, Wang
    Chen, Wei-Hua
    Yu, Su-Yuan
    NUCLEAR POWER PLANTS: INNOVATIVE TECHNOLOGIES FOR INSTRUMENTATION AND CONTROL SYSTEMS, 2017, 400 : 125 - 132