Main steam-line break core shroud loading calculations for BWRs

Journal Article · Sun Dec 31 04:00:00 EST 1995 · Transactions of the American Nuclear Society

OSTI ID:411677

Shoop, U; Feltus, M A; Baratta, A J ^[1]

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1. 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--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
CONTROL ELEMENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SAFETY ANALYSIS
SHROUDS
STRESS CORROSION
T CODES