BWR containment failure analysis during degraded-core accidents

Conference · Sun Jun 06 00:00:00 EDT 1982

OSTI ID:5338909

Yue, D D

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

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
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
STRESSES
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled