Exploiting digital systems technology to improve nuclear safety
Creators
- 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)
Description
Nuclear plant designers in the 1990's have exceptional opportunities to exploit rapidly evolving computer and information system technology to make significant improvements in public safety. CANDU reactors have utilized extensive computer automation for reactor control for 20 years. A direct consequence is that the frequencies for forced outages and spurious protection system trips have been among the lowest for all reactor types. Historically, CANDU was among the first commercial power reactor to utilize computers to implement protection system. System functions with the PDC's (Programmable Digital Comparators) used in the CANDU 600 reactors. PDC's were used to implement the trip decision logic for the process trip parameters. The paper provides detail on safety benefits that have been realized from the use of digital automation for control and protection. The paper describes how accident risk reduction can be achieved in other ways with digital systems
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 3, Structural engineering; Advanced reactor research; Advanced passive reactors; Human factors research; Human factors issues related to advanced passive LWRs; Thermal hydraulics; Earth sciences
- Imprint Pagination
- 542 p.
- Journal Page Range
- p. 141-160.
- Report number
- NUREG/CP--0119-Vol.3
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24027058
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALARM SYSTEMS; ATOMIC ENERGY OF CANADA LTD; AUTOMATION; AVAILABILITY; CANADA; CANDU TYPE REACTORS; CONTROL ROOMS; DARLINGTON-1 REACTOR; DESIGN; DIGITAL SYSTEMS; DOCUMENTATION; ENGINEERED SAFETY SYSTEMS; ENGINEERING; ERRORS; FAILURES; GENTILLY-2 REACTOR; HUMAN FACTORS; INFORMATION SYSTEMS; MAN-MACHINE SYSTEMS; MANAGEMENT; PERFORMANCE; POINT LEPREAU-1 REACTOR; POINT LEPREAU-2 REACTOR; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; REACTOR OPERATION; REACTOR OPERATORS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REAL TIME SYSTEMS; RELIABILITY; RISK ASSESSMENT; SCRAM; STANDARDIZATION; WOLSUNG-1 REACTOR
- Descriptors DEC
- ACCIDENTS; CANADIAN ORGANIZATIONS; CONTROL SYSTEMS; DEVELOPED COUNTRIES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATIONAL ORGANIZATIONS; NATURAL URANIUM REACTORS; NORTH AMERICA; OPERATION; PERSONNEL; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--Vol.3.