Published February 1991 | Version v1
Report

Application of computers for control and protection functions in research and power reactors

  • 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Control Div.

Description

This paper describes the application of Computer/Microcomputer based systems in Indian Reactors at present and in future. The concepts of fault tolerance, redundancy, isolation of control and safety functions, avoidance of error propagation, continuous monitoring and diagnostics are being followed in all configurations. Many standalone systems have been designed and installed for Research Reactors DHRUVA, KAMINI and 235 MWe PHWRs. Whereas for 235 MWe programme, the task has been to upgrade and modernize existing controls, the 500 MWe arena is mainly for developing new concepts. 6 figs, 2 tabs

Part of:
Safety implications of computerized process control in nuclear power plants

Additional details

Publishing Information

Imprint Title
Safety implications of computerized process control in nuclear power plants
Imprint Pagination
192 p.
Journal Page Range
p. 113-129.
Report number
IAEA-TECDOC--581

Conference

Title
Technical committee meeting on safety implications of computerized process control in nuclear power plants.
Dates
13-17 Nov 1989.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
22038172
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; COMPUTERS; PHWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RELIABILITY; SPECIFICATIONS
Descriptors DEC
CONTROL SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; REACTORS; SAFETY

Optional Information