BWR containment failure analysis during degraded-core accidents
Conference
·
OSTI ID:5338909
This paper presents a containment failure mode analysis during a spectrum of postulated degraded core accident sequences in a typical 1000-MW(e) boiling water reactor (BWR) with a Mark-I wetwell containment. Overtemperature failure of containment electric penetration assemblies (CEPAs) has been found to be the major failure mode during such accidents.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5338909
- Report Number(s):
- CONF-820609-55; ON: DE82017432; TRN: 82-015961
- Resource Relation:
- Conference: American Nuclear Society annual meeting, Los Angeles, CA, USA, 6 Jun 1982
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT SYSTEMS
FAILURE MODE ANALYSIS
REACTOR ACCIDENTS
REACTOR SAFETY
THERMAL STRESSES
ACCIDENTS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
REACTORS
SAFETY
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SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
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Light-Water Moderated
Boiling Water Cooled