Reliability analysis of microcomputer circuit modules and computer based control systems important to safety of nuclear power plants

被引:5
|
作者
Khobare, SK [1 ]
Shrikhande, SV [1 ]
Chandra, U [1 ]
Govindarajan, G [1 ]
机构
[1] Bhabha Atom Res Ctr, Reactor Control Div, Mumbai 400085, India
关键词
D O I
10.1016/S0951-8320(97)00151-8
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Computer based safety related control and instrumentation (C&I) systems are being employed in Indian Nuclear Power Plants (NPPs). These systems are designed around standardized family of microcomputer based circuit modules, which are qualified to the stringent requirements of the nuclear industry. Reliability analysis of standardized microcomputer circuit modules, used in the safety related C&I systems, were carried out using the analysis package based on the methodology and database of MIL-STD-217-F1. The circuit modules are the main building blocks of the safety related C&I systems in the forthcoming Indian NPPs. The article presents reliability analysis results of microcomputer and related circuit modules and a representative safety C&I system-Programmable Digital Comparator System (PDCS). Comparison of reliability values for prototype PDCS using commercial grade components, and for upgraded version PDCS using MIL grade or equivalent screened components was made. The estimated failure rate values of standardized microcomputer circuit modules will be useful, for reliability assessment of various other safety related C&I systems developed around these modules, for ongoing and future Indian NPPs. (C) 1998 Elsevier Science Limited.
引用
收藏
页码:253 / 258
页数:6
相关论文
共 50 条
  • [21] Probabilistic safety assessment for instrumentation and control systems in nuclear power plants: An overview
    Lu, LX
    Jiang, J
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2004, 41 (03) : 323 - 330
  • [22] ASCERTAINING QUALITY FOR SAFETY AND RELIABILITY IN NUCLEAR-POWER PLANTS
    NICOLOSO, E
    ELETTROTECNICA, 1972, 59 (07): : 786 - &
  • [23] Reliability analysis of digital reactor protection systems in floating nuclear power plants
    Xie, Xi-Wen
    Yin, Chang-Zheng
    Peng, Chang-Hong
    KERNTECHNIK, 2024, 89 (04) : 504 - 518
  • [24] Reliability data process and analysis of instrument and control switch in nuclear power plants
    Shi, Jie
    Shen, Deng-Hua
    Shi, Hai-Ning
    Tu, Feng-Sheng
    Hedongli Gongcheng/Nuclear Power Engineering, 2010, 31 (02): : 54 - 57
  • [25] APPLICATION OF DIGITAL COMPUTER SYSTEMS IN NUCLEAR POWER PLANTS
    BEVILACQUA, F
    YUILE, EA
    IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 1969, NS16 (01) : 196 - +
  • [26] A QUANTITATIVE APPROACH FOR RELIABILITY EVALUATION OF SAFETY I&C SYSTEMS IN NUCLEAR POWER PLANTS
    Liu Dongxu
    Xu Dongling
    Zhang Shuhui
    Hu Xiaoying
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 1, 2017,
  • [27] RELIABILITY ESTIMATION FOR IMPORTANT NUCLEAR-POWER STATION SAFETY EQUIPMENT
    PEREGUDA, AI
    CHEKHOVICH, VE
    SUKHETSKII, AK
    ATOMIC ENERGY, 1992, 73 (04) : 784 - 788
  • [28] A computer based living probabilistic safety assessment (LPSA) method for nuclear power plants
    Zubair, Muhammad
    Zhang Zhijian
    Heo, Gyunyoung
    Ahmed, Iftikhar
    Aamir, Muhammad
    NUCLEAR ENGINEERING AND DESIGN, 2013, 265 : 765 - 771
  • [29] SAFETY AND RELIABILITY IN COMPUTER-BASED SYSTEMS
    DALE, C
    DATA PROCESSING, 1984, 26 (10): : 11 - &
  • [30] RELIABILITY OF COMPUTER-BASED SAFETY SYSTEMS
    ONSHUS, T
    BODSBERG, L
    COMPUTERS AND SAFETY: A FIRST INTERNATIONAL CONFERENCE ON THE USE OF PROGRAMMABLE ELECTRONIC SYSTEMS IN SAFETY RELATED APPLICATIONS, 1989, 314 : 8 - 12