MELCOR computer code manuals: Primer and user`s guides, Version 1.8.3 September 1994. Volume 1

Technical Report · Wed Mar 01 04:00:00 EST 1995

DOI:https://doi.org/10.2172/61164· OSTI ID:61164

Summers, R M; Cole, Jr, R K; Smith, R C; Stuart, D S; Thompson, S L ^[1]; Hodge, S A; Hyman, C R; Sanders, R L ^[2]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Oak Ridge National Lab., TN (United States)

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the US Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR`s phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users` Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; Sandia National Labs., Albuquerque, NM (United States); Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 61164
• Report Number(s): NUREG/CR--6119-Vol.1; SAND--93-2185-Vol.1; ON: TI95010659
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
BWR TYPE REACTORS
COMPUTER PROGRAM DOCUMENTATION
ENGINEERED SAFETY SYSTEMS
HEAT TRANSFER
HYDRAULICS
M CODES
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
SENSITIVITY ANALYSIS