TRAC-BF1 thermal-hydraulic, ANSYS stress analysis for core shroud cracking phenomena

Journal Article · Tue Dec 31 00:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:426484

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

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1. 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-; ISSN 0003-018X; TRN: 96:006307-0213
• Journal Information: Transactions of the American Nuclear Society, Vol. 75; Conference: Winter meeting of the American Nuclear Society (ANS) and the European Nuclear Society (ENS), Washington, DC (United States), 10-14 Nov 1996; Other Information: PBD: 1996
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
SHROUDS
STRESS CORROSION
SAFETY ANALYSIS
INTERGRANULAR CORROSION
CRACK PROPAGATION
BWR TYPE REACTORS
T CODES
HYDRAULICS
STRESS ANALYSIS
A CODES
STEAM SYSTEMS