United States Nuclear Regulatory Commission - Protecting People and the Environment

MELCOR Recent Developments

Sponsored by the Office of Nuclear Regulatory Research

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 developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework.

This poster presentation will show the regulatory applications of MELCOR supported by domestic and international research on severe accident phenomenology. A description of active arears of code development is provided along with the most recent applications of the code including spent fuel pool modeling, Fukushima accident analysis, support for containment protection and release reduction rulemaking, and Vogtle site Level 3 probabilistic risk assessment.

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Page Last Reviewed/Updated Friday, June 26, 2015