Main steam-line break core shroud loading calculations for BWRs
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:411677
- Pennsylvania State Univ., University Park, PA (United States)
In July 1994, the U.S. Nuclear regulatory Commission sent out Generic Letter 94-03 to all boiling water reactors in the United States, informing them of intergranular stress corrosion cracking of core shrouds found in 2 reactors. The letter directed all to perform safety analysis of the BWR units. Penn State performed scoping calculations to determine the forces experienced by the core shroud during a main-stream line break transient.
- OSTI ID:
- 411677
- Report Number(s):
- CONF-951006-; ISSN 0003-018X; TRN: 97:000926
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 73; Conference: Winter meeting of the American Nuclear Society (ANS), San Francisco, CA (United States), 29 Oct - 1 Nov 1995; Other Information: PBD: 1995
- Country of Publication:
- United States
- Language:
- English
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