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

来源：

RELIABILITY ENGINEERING & SYSTEM SAFETY | 1998年 / 59卷 / 02期

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

页码：253 / 258

页数：6

共 50 条

[31] Dynamic reliability analysis framework for passive safety systems of Nuclear Power Plant
Tripathi, A. Manish
Singh, B. Lalit Kumar
Singh, C. Suneet
ANNALS OF NUCLEAR ENERGY, 2020, 140
[32] Reliability and Safety of Nuclear Power Plant Instrumentation and Control Systems: New Challenges and Solutions
Yastrebenetsky, Mikhail
Kharchenko, Vyacheslav
2016 SECOND INTERNATIONAL SYMPOSIUM ON STOCHASTIC MODELS IN RELIABILITY ENGINEERING, LIFE SCIENCE AND OPERATIONS MANAGEMENT (SMRLO), 2016, : 47 - 55
[33] Development of ASIC and PLC-based safety systems for nuclear power plants
Naser, J
PROCEEDINGS OF THE AMERICAN POWER CONFERENCE, VOL. 60, PTS I & II, 1998, : 741 - 745
[34] RELIABILITY AND RISK ANALYSIS OF NUCLEAR-POWER PLANTS
KINKEAD, AN
NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1984, 23 (01): : 55 - 64
[35] Design of safety critical and control systems of Nuclear Power Plants using Petri nets
Singh, Pooja
Singh, Lalit Kumar
NUCLEAR ENGINEERING AND TECHNOLOGY, 2019, 51 (05) : 1289 - 1296
[36] Verification of safety critical and control systems of Nuclear Power Plants using Petri nets
Singh, Pooja
Singh, Lalit
ANNALS OF NUCLEAR ENERGY, 2019, 132 : 584 - 592
[37] APPLICATION OF PROBABILISTIC SAFETY ASSESSMENT IN THE DESIGN OF INSTRUMENTATION AND CONTROL SYSTEMS FOR NUCLEAR POWER PLANTS
Peng, Pengyi
Liu, Weidong
Yang, Zhichao
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 4, 2017,
[38] RELIABILITY OF LARGE, EQUIPMENT AND SYSTEMS OF NUCLEAR-POWER PLANTS
HASHMI, MF
MICROELECTRONICS AND RELIABILITY, 1978, 17 (01): : 99 - 104
[39] Safety, reliability, human factors, and human error in nuclear power plants
Swinson, Lucy
ERGONOMICS, 2018, 61 (11) : 1569 - 1570
[40] INCREASE OF SAFETY AND RELIABILITY OF VAPOR GENERATORS ON NUCLEAR-POWER PLANTS
KOLMAS, O
JADERNA ENERGIE, 1984, 30 (8-9): : 335 - 335

← 1 2 3 4 5 →