MELCOR analysis of the NRU Full-Length High-Temperature-2 test

Conference · Mon Dec 31 23:00:00 EST 1990 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5854401

Madni, I K; Guo, X D; Nimnual, S; Pratt, W T ^[1]

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1. Brookhaven National Lab., Upton, NY (United States)

MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in nuclear power plants. It is being developed for the US Nuclear Regulatory Commission by Sandia National Laboratories and is designed to provide an improved severe-accident/source term analysis capability relative to the older Source Term Code Package. Early assessment efforts for MELCOR emphasized validation of containment modeling. Current assessment efforts have realized the need to focus more on in-vessel phenomenology, which is an area of major uncertainty in the assessment of severe-accident radiological consequences. In-vessel analyses reported to date using MELCOR have been the Power Burst Facility (PBF) SFD 1-1 test, the Three Mile Island Unit 2 standard problem, both using MELCOR Version 1.7.1, and the PBF SFD 1-4 test, which used MELCOR Version 1.8BC. The purpose of this paper is to describe a MELCOR (Version 1.8DN, the most recent) simulation of the National Research Universal (NRU) Full-Length High-Temperature 2 (FLHT-2) test and to compare results with test data and predictions from the US Nuclear Regulatory Commission's mechanistic code SCDAP.

• OSTI ID: 5854401
• Report Number(s): CONF-910603--
• Journal Information: Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 63; ISSN TANSA; ISSN 0003-018X
• Country of Publication: United States
• Language: English

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