Oak Ridge National Lab., TN (United States).Sandia National Labs., Albuquerque, NM (United States).Volume 2 contains the MELCOR Reference Manuals, which more » describe the phenomenological models that have been implemented in each package. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package.
Volume 1 contains a primer that describes MELCOR`s phenomenological scope, organization (by package), and documentation. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. 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. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. MELCOR is being developed at Sandia National Laboratories for the U.S. MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants.
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