Safety and reliability aspects of microcomputer based control systems in nuclear power plants
Description
Full text: Computer based control and instrumentation (C and I) systems are increasingly being used in safety related and safety critical control applications in the current 220 MWe Indian PHWRs. System reliability group (SRG) in RCnD has carried out reliability analysis of the safety important C and I systems like DPHS-PCS, DPHS-RRS and PDCS employed in Kaiga-l, 2 and RAPS-3, 4. The control systems were designed and developed jointly by RCnD and NPCIL C and I design groups. The paper details the various issues related to the fault tolerant design, essential qualification and reliability of the circuit hardware, required for the C and I system design to meet the target reliability/availability values, as specified in IAEA and other International standards. The similar methodology is planned for the forthcoming 500 MWe PHWRs (TAPP-3, 4), and future AHWR
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- First national conference on nuclear reactor technology
- Imprint Pagination
- 421 p.
- Journal Page Range
- p. 322
Conference
- Title
- 1. nuclear reactor safety
- Acronym
- NRT-1
- Dates
- 25-27 Nov 2002
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 34011384
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HWLWR TYPE REACTORS; KAIGA-1 REACTOR; KAIGA-2 REACTOR; POWER RANGE 100-1000 MW; REACTOR CONTROL SYSTEMS; REACTOR SAFETY; RELIABILITY
- Descriptors DEC
- CANDU TYPE REACTORS; CONTROL SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MEGAWATT POWER RANGE; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER RANGE; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS