Reactivity accidents: A reassessment of the design-basis events
- 1. Brookhaven National Lab., Upton, NY (USA)
Description
This paper summarizes a study of light water reactor event sequences which have been investigated for their potential to result in reactivity accidents with severe consequences. The study is an outgrowth of the concern which arose after the accident at Chernobyl and was recommended by the report of the US Nuclear Regulatory Commission (NRC) on the implications of that accident (NUREG-1251). The work was done for the NRC to reconfirm or bring into question previous judgments on reactivity events which must be analyzed for licensing. Event sequences were defined and then a probabilistic assessment was completed to estimate the frequency of the reactivity event and/or a deterministic calculation was completed to estimate the consequences to the fuel. Using the results of this analysis, analysis done by others, and a set of screening criteria developed within this study, judgments were made for each sequence as to its importance, and recommendations were made as to whether the NRC ought to be considering the important sequences as part of the design basis or for further, more detailed investigation
Additional details
Publishing Information
- Imprint Title
- Seventeenth water reactor safety information meeting: Proceedings. Volume 2, Accident management; severe accident research; earth sciences; probabilistic risk assessment; seismic and structural engineering
- Imprint Pagination
- 515 p.
- Journal Page Range
- p. 91-115.
- Report number
- NUREG/CP--0105-Vol.2
Conference
- Title
- 17. water reactor safety information meeting.
- Dates
- 23-25 Oct 1989.
- Place
- Rockville, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22091236
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; BLOWDOWN; BWR TYPE REACTORS; CHERNOBYLSK-4 REACTOR; CRITICALITY; EMERGENCY PLANS; EXCURSIONS; FAILURE MODE ANALYSIS; FLOW MODELS; FUEL ELEMENT FAILURE; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTIVITY; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR KINETICS; REACTOR LICENSING; REACTOR PERIOD; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RESEARCH PROGRAMS; RISK ASSESSMENT; ROD DROP ACCIDENTS; SCRAM; STRATIFICATION; US NRC; VALVES
- Descriptors DEC
- ACCIDENTS; CONTROL EQUIPMENT; COOLING SYSTEMS; DESIGN BASIS ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; GRAPHITE MODERATED REACTORS; KINETICS; LICENSING; LWGR TYPE REACTORS; MATHEMATICAL MODELS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTIVITY INSERTIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC02-76CH00016
- Secondary number(s)
- CONF-8910222--Vol.2.