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MELCOR is developed at
Sandia National Laboratories
for the
U.S. Nuclear Regulatory Commission
|
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. MELCOR applications include estimation of severe accident
source terms, and their sensitivities and uncertainties in a variety of
applications. MELCOR is also used to analyze design basis accidents for
advanced plant applications (ESBWR, EPR, APWR). |
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Just released: MELCOR Version 2.1
