TRAC-BF1 thermal-hydraulic, ANSYS stress analysis for core shroud cracking phenomena
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:426484
- Pennsylvania State Univ., University Park, PA (United States)
The U.S. Nuclear Regulatory Commission sent Generic Letter 94-03 informing all licensees about the intergranular stress corrosion cracking (IGSCC) of core shrouds found in both Dresden unit I and Quad Cities unit 1. The letter directed all licensees to perform safety analysis of their boiling water reactor (BWR) units. Two transients of special concern for the core shroud safety analysis include the main steam line break (MSLB) and recirculation line break transient.
- OSTI ID:
- 426484
- Report Number(s):
- CONF-961103--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 75; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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