An interpretation of accident precursor data
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6958960
- Nuclear Regulatory Commission, Washington, DC (United States)
The Accident Sequence Precursor (ASP) program, managed by the U.S. Nuclear Regulatory Commission, utilizes probabilistic modeling methods to evaluate significant nuclear power plant operating experiences. The operating experiences assessed are operating events or plant conditions reported by the licensees, which are deemed important elements of postulated core damage scenarios. If additional events occur, the postulated scenarios could be completed and result in loss of reactor core cooling. The ASP program uses event trees to model plant operating events or incidents. Failures that actually occurred are quantified by their nonrecovery likelihoods. Random probabilities are assigned for other events that might have occurred in combination and led to postulated core damaging accident scenarios. Results of the ASP program were reported in two recent papers.
- OSTI ID:
- 6958960
- Report Number(s):
- CONF-931160--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
- Country of Publication:
- United States
- Language:
- English
Similar Records
Core damage frequency estimation using accident sequence precursor data: 1990--1993
Precursors to potential severe core damage accidents, 1986: A status report: Main report and Appendixes A,B, and C
1995 Accident Sequence Precursor (ASP) Program results
Conference
·
Mon Nov 30 23:00:00 EST 1998
·
OSTI ID:291102
Precursors to potential severe core damage accidents, 1986: A status report: Main report and Appendixes A,B, and C
Technical Report
·
Sun May 01 00:00:00 EDT 1988
·
OSTI ID:5155301
1995 Accident Sequence Precursor (ASP) Program results
Journal Article
·
Tue Dec 31 23:00:00 EST 1996
· Nuclear Safety
·
OSTI ID:642366
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FAILURE MODE ANALYSIS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
POWER PLANTS
PRECURSOR
PROBABILISTIC ESTIMATION
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR OPERATION
REACTOR SAFETY
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FAILURE MODE ANALYSIS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
POWER PLANTS
PRECURSOR
PROBABILISTIC ESTIMATION
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR OPERATION
REACTOR SAFETY
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS