Approach to numerical safety guidelines based on a core melt criterion. [PWR; BWR]
A plausible approach is proposed for translating a single level criterion to a set of numerical guidelines. The criterion for core melt probability is used to set numerical guidelines for various core melt sequences, systems and component unavailabilities. These guidelines can be used as a means for making decisions regarding the necessity for replacing a component or improving part of a safety system. This approach is applied to estimate a set of numerical guidelines for various sequences of core melts that are analyzed in Reactor Safety Study for the Peach Bottom Nuclear Power Plant.
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- OSTI ID:
- 5371056
- Report Number(s):
- BNL-NUREG-30899; CONF-820609-22; ON: DE82009188; TRN: 82-011615
- Resource Relation:
- Conference: American Nuclear Society annual meeting, Los Angeles, CA, USA, 6 Jun 1982
- Country of Publication:
- United States
- Language:
- English
Similar Records
A probabilistic safety criterion for core melt frequency based on the distribution of the public's safety goals
Seismic safety margins research program. Phase I. Project VII: systems analysis specifications of computational approach. [PWR; BWR]
Precursors to potential severe core-damage accidents: 1969-1979 a status report. [PWR; BWR]
Journal Article
·
Mon Feb 01 00:00:00 EST 1993
· Nuclear Technology; (United States)
·
OSTI ID:5371056
Seismic safety margins research program. Phase I. Project VII: systems analysis specifications of computational approach. [PWR; BWR]
Technical Report
·
Thu Feb 01 00:00:00 EST 1979
·
OSTI ID:5371056
Precursors to potential severe core-damage accidents: 1969-1979 a status report. [PWR; BWR]
Technical Report
·
Tue Jun 01 00:00:00 EDT 1982
·
OSTI ID:5371056
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
MELTDOWN
PROBABILITY
PWR TYPE REACTORS
MATHEMATICAL MODELS
REACTOR SAFETY
ACCIDENTS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
MELTDOWN
PROBABILITY
PWR TYPE REACTORS
MATHEMATICAL MODELS
REACTOR SAFETY
ACCIDENTS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled