Synergistic Failure of BWR Internals
Boiling Water Reactor (BWR) core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, with specific consideration given to potential cascading and common mode effects. An initial phase has been completed in which background material was gathered and evaluated, and potential accident sequences were identified. A second phase is underway to perform a simplified, quantitative probabilistic risk assessment on a representative high-power BWR/4. Results of the initial study conducted on the jet pumps show that any cascading failures would not result in a significant increase in the core damage frequency. The methodology is currently being extended to other major reactor internals components.
- Research Organization:
- Idaho National Laboratory (INL)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC07-99ID13727
- OSTI ID:
- 911353
- Report Number(s):
- INEEL/CON-99-01142
- Country of Publication:
- United States
- Language:
- English
Similar Records
A Program for Risk Assessment Associated with IGSCC of BWR Vessel Internals
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Related Subjects
ACCIDENTS
BOILING
Boiling Water Reactor
INEEL
REACTOR COMPONENTS
REACTOR SAFETY
RISK ASSESSMENT
SAFETY
SHROUDS
STRESS CORROSION
WATER
accident sequences
cascading failures
core shrouds
intergranular stress corrosion cracking (IGSCC)
risk assessment
vessel internals