MELCOR Peer Review

Technical Report · Sun Mar 01 00:00:00 EST 1992

DOI:https://doi.org/10.2172/10139479· OSTI ID:10139479

Boyack, B E ^[1]; Dhir, V K ^[2]; Gieseke, J A ^[3]; Haste, T J ^[4]; Kenton, M A ^[5]; Khatib-Rahbar, M ^[6]; Leonard, M T ^[7]; Viskanta, R ^[8]

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1. Los Alamos National Lab., NM (United States)
2. Santa Monica, CA. (United States)
3. Battelle, Columbus, OH (United States)
4. AEA Technology, Winfrith (United Kingdom)
5. Gabor, Kenton and Associates, Inc., Westmont, IL (United States)
6. Energy Research, Inc., Rockville, MD (United States)
7. Science Applications International Corp., Wolfheze (Netherlands)
8. Purdue Univ., Lafayette, IN (United States). Heat Transfer Lab.

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. The newest version of MELCOR is Version 1.8.1, July 1991. MELCOR development has reached the point that the United States Nuclear Regulatory Commission sponsored a broad technical review by recognized experts to determine or confirm the technical adequacy of the code for the serious and complex analyses it is expected to perform. For this purpose, an eight-member MELCOR Peer Review Committee was organized. The Committee has completed its review of the MELCOR code: the review process and findings of the MELCOR Peer Review Committee are documented in this report. The Committee has determined that recommendations in five areas are appropriate: (1) MELCOR numerics, (2) models missing from MELCOR Version 1.8.1, (3) existing MELCOR models needing revision, (4) the need for expanded MELCOR assessment, and (5) documentation.

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 10139479
• Report Number(s): LA-12240; LA-SUB-92-7; ON: DE92012220; TRN: 92:016722
• Resource Relation: Other Information: PBD: Mar 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
M CODES
EVALUATION
REACTOR ACCIDENTS
COMPUTERIZED SIMULATION
PWR TYPE REACTORS
BWR TYPE REACTORS
NUCLEAR POWER PLANTS
FLOWSHEETS
REACTOR SAFETY
220900
210100
210200
990200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MATHEMATICS AND COMPUTERS