Preliminary Risk Assessment Associated with IGSCC of BWR Vessel Internals
- Lockheed Martin Idaho Technologies Company
- INEEL
- USNRC
BWR core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission (NRC) has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory (INEEL) 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. The paper presents an overview of the program, discusses the results of a preliminary qualitative assessment, and summarizes a simplified risk assessment that was conducted on sequences resulting from failures of jet pump components of a BWR/4 plant.
- Research Organization:
- Idaho National Engineering and Environmental Lab., Idaho Falls, ID (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC07-94ID13223
- OSTI ID:
- 8199
- Report Number(s):
- INEEL/CON-99-00264
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BWR CORE SHROUDS
BWR TYPE REACTORS
CASCADING AND COMMON MODE EFFECTS
CRACK PROPAGATION
GENERAL DESIGN CRITERIA 2 AND 4
INTERGRANULAR STRESS CORROSION CRACKING (IGSCC)
JET PUMP COMPONENTS
NATURAL PHENOMENA
PLANT SAFETY
POSTULATED ACCIDENTS
REACTOR COMPONENTS
RISK ASSESSMENT
SAFETY ENGINEERING
SHROUDS
STRESS CORROSION