The application of probabilistic fracture analysis to residual life evaluation of embrittled reactor vessels
- Oak Ridge National Lab., TN (United States)
- Pacific Northwest Lab., Richland, WA (United States)
Probabilistic fracture mechanics analysis is a major element of comprehensive probabilistic methodology on which current NRC regulatory requirements for pressurized water reactor vessel integrity evaluation are based. Computer codes such as OCA-P and VISA-II perform probabilistic fracture analyses to estimate the increase in vessel failure probability that occurs as the vessel material accumulates radiation damage over the operating life of the vessel. The results of such analyses, when compared with limits of acceptable failure probabilities, provide an estimation of the residual life of a vessel. Such codes can be applied to evaluate the potential benefits of plant-specific mitigating actions designed to reduce the probability of failure of a reactor vessel. 10 refs.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10141972
- Report Number(s):
- CONF-920375-14; ON: DE92013289
- Resource Relation:
- Conference: Aging research information conference,Rockville, MD (United States),24-27 Mar 1992; Other Information: PBD: [1992]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR VESSELS
FRACTURE MECHANICS
O CODES
V CODES
PWR TYPE REACTORS
EMBRITTLEMENT
PROBABILISTIC ESTIMATION
REACTOR SAFETY
HEAT TRANSFER
HYDRAULICS
FAILURES
MITIGATION
220900
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED