Progress in MELCOR development and assessment

Conference · Sat Oct 01 00:00:00 EDT 1994

OSTI ID:54568

Summers, R M; Kmetyk, L N; Cole, Jr, R K; Smith, R C; Elsbernd, A E; Stuart, D S; Thompson, S L ^[1]

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1. Sandia National Labs., Albuquerque, NM (United States)

Recent activities in the MELCOR development project have focused on (1) addressing difficulties with CORCON-Mod3 and implementing a robust and reliable version into the demanding systems code environment of MELCOR; (2) developing and implementing models for specific phenomena and systems of importance to advanced reactors; and (3) continuing to expand the MELCOR assessment data base, filling in the gaps in phenomenological coverage. Excellent progress has been made, resulting in a much-improved version of the code: MELCOR 1.8.3, distributed to users in July 1994. This version of the code received substantial testing on a suite of plant and experiment calculations prior to release.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 54568
• Report Number(s): NUREG/CP-0139; CONF-9410216-; ON: TI95001469; TRN: 95:012602
• Resource Relation: Conference: 22. water reactor safety information meeting, Bethesda, MD (United States), 24-26 Oct 1994; Other Information: PBD: Oct 1994; Related Information: Is Part Of Transactions of the twenty-second water reactor safety information meeting; PB: 129 p.
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
22 NUCLEAR REACTOR TECHNOLOGY
THERMAL ANALYSIS
COMPUTERIZED SIMULATION
WATER COOLED REACTORS
NUCLEAR POWER PLANTS
REACTOR SAFETY
CONTAINMENT SYSTEMS
M CODES