Actions for Preliminary Risk Assessment Associated with IGSCC of BWR Vessel Internals [electronic resource].
Preliminary Risk Assessment Associated with IGSCC of BWR Vessel Internals [electronic resource].
- Published
- Washington, D.C. : United States. Dept. of Energy, 1999.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- 9 pages : digital, PDF file
- Additional Creators
- Idaho National Engineering and Environmental Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- 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.
- Report Numbers
- E 1.99:ineel/con-99-00264
ineel/con-99-00264 - Subject(s)
- Other Subject(s)
- Bwr Type Reactors
- Reactor Components
- Risk Assessment
- Safety Engineering
- Shrouds
- Stress Corrosion
- Crack Propagation
- Bwr Core Shrouds
- Intergranular Stress Corrosion Cracking (Igscc)
- Risk Assessment
- Cascading And Common Mode Effects
- Jet Pump Components
- General Design Criteria 2 And 4
- Natural Phenomena
- Postulated Accidents
- Plant Safety
- Note
- Published through SciTech Connect.
08/01/1999.
"ineel/con-99-00264"
15th Structural Mechanics in Reactor Technology Conference (SMiRT-15), Seoul (KR), 08/15/1999--08/20/1999.
N. Chokshi; A. Ware; M. Nitzel; K. Morton; T-Y. Chang. - Funding Information
- AC07-94ID13223
View MARC record | catkey: 14800973