Comparison of MELCOR and SCDAP/RELAP5 results for a low-pressure, short-term station blackout at Browns Ferry

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

OSTI ID:411681

Carbajo, J J ^[1]

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1. Oak Ridge National Lab., TN (United States)

This study compares results obtained with two U.S. Nuclear Regulatory Commission (NRC)-sponsored codes, MELCOR version 1.8.3 (1.8PQ) and SCDAP/RELAP5 Mod3.1 release C, for the same transient - a low-pressure, short-term station blackout accident at the Browns Ferry nuclear plant. This work is part of MELCOR assessment activities to compare core damage progression calculations of MELCOR against SCDAP/RELAP5 since the two codes model core damage progression very differently.

• OSTI ID: 411681
• 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
BROWNS FERRY-1 REACTOR
COMPARATIVE EVALUATIONS
CONTAINMENT
M CODES
REACTOR SAFETY
S CODES
TRANSIENTS