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	Get a MELCOR Download Account MELCOR Download Login FAQs 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).	TECHNICAL REVIEW MEETINGS CSARP/MCAP 2008 Meeting Bethesda, Maryland Announcement Preliminary Program Agenda [coming soon] REGISTER NOW! September 8-9 MACCS2 1-1/2-day Workshop September 9-12 MELCOR 3-1/2-day Beginner Workshop September 15 MELCOR 1-day Workshop for Advanced Users September 16-19 CSARP/MCAP 4-day Meeting >>> Past Meetings TECHNICAL LIBRARY Reports Presentations NEWS Labs Accomplishments 2008, Energy >>> News archives
	GALLERY [>>> More] Randy Cole and Randy Gauntt MELCOR software CD cover Prestressed concrete containment vessel (PCCV)
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