Independent assessment of MELCOR as a severe accident thermal-hydraulic/source term analysis tool

Conference · Sat Jan 01 04:00:00 EST 1994

OSTI ID:10115024

Madni, I K ^[1]; Eltawila, F ^[2]

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1. Brookhaven National Lab., Upton, NY (United States)
2. Nuclear Regulatory Commission, Washington, DC (United States)

MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in light water reactor nuclear power plants, and is being developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratories (SNL). Brookhaven National Laboratory (BNL) has a program with the NRC called ``MELCOR Verification, Benchmarking, and Applications,`` whose aim is to provide independent assessment of MELCOR as a severe accident thermal-hydraulic/source term analysis tool. The scope of this program is to perform quality control verification on all released versions of MELCOR, to benchmark MELCOR against more mechanistic codes and experimental data from severe fuel damage tests, and to evaluate the ability of MELCOR to simulate long-term severe accident transients in commercial LWRs, by applying the code to model both BWRs and PWRs. Under this program, BNL provided input to the NRC-sponsored MELCOR Peer Review, and is currently contributing to the MELCOR Cooperative Assessment Program (MCAP). This paper presents a summary of MELCOR assessment efforts at BNL and their contribution to NRC goals with respect to MELCOR.

• Research Organization: Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 10115024
• Report Number(s): BNL-NUREG--49018; CONF-940518--1; ON: DE94005191
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
BENCHMARKS
BWR TYPE REACTORS
EVALUATION
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
M CODES
MATHEMATICS AND COMPUTERS
NUCLEAR POWER PLANTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
QUALITY CONTROL
REACTOR ACCIDENTS
REACTOR SAFETY
SOURCE TERMS