New MELCOR documentation available.

     

 

line
Get MELCOR

line
Downloads

line
FAQs

line

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).

line
TECHNICAL REVIEW MEETINGS

(No technical review meetings scheduled)


line
TECHNICAL LIBRARY

Reports
Presentations

New! MELCOR Documentation
line
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

line
GALLERY [>>> More]

pict
Randy Cole and
Randy Gauntt

pict
MELCOR software
CD cover

pict
Prestressed concrete containment vessel (PCCV)

Sandia National Laboratories | U.S. Nuclear Regulatory Commission
© Sandia Corporation | Site Contact | Privacy and Security