MELCOR Computer Code Manuals Volume 1: Primer and Users' Guide

Technical Report · Sat Aug 01 00:00:00 EDT 2015

DOI:https://doi.org/10.2172/1433069· OSTI ID:1433069

Humphries, Larry L. ^[1]; Figueroa, Victor G. ^[1]; Young, Michael F. ^[1]; Louie, David ^[1]; Reynolds, John Thomas ^[1]

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1. Sandia National Lab. (SNL-NM), Albuquerque, NM (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 U.S. 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 behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications.

• Research Organization: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: USNRC; USDOE
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 1433069
• Report Number(s): SAND-2015-6691R; 662141
• Country of Publication: United States
• Language: English