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Nuclear Energy Safety Technologies


Severe Accident Modeling
Fact Sheets



Fukushima Daiichi Accident
(Status as of April 2012)
Study SAND2012-6173

melcor
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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TECHNICAL REVIEW MEETINGS

2014
CSARP/MCAP/IMUG/MELCOR
Register for event(s) here


Dates:
MELCOR User’s workshop
9/8/14 - 9/12/14

Cooperative Severe Accident Research Program (CSARP) / MELCOR Code Assessment Program (MCAP) Meeting / International MACCS Users Group (IMUG) Meeting
9/15/14 - 9/19/14

Official CSARP/MCAP/IMUG Announcement

CSARP/MCAP/IMUG Agenda (coming soon)

MELCOR Workshop Agenda

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TECHNICAL LIBRARY

Reports

Presentations

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NEWS

Modeling the Fukushima accident: MELCOR code used to model accidents at Fukushima, August 2012

Labs Accomplishments 2008, Energy

>>> News archives

nrc

MELCOR is developed at
Sandia National Laboratories
for the
U.S. Nuclear Regulatory Commission
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