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Code Owner: Sandia National Laboratory (SNL)

Description: MELCOR (Methods for Estimation of Leakages and Consequences of Releases) is a fully integrated, engineering-level computer code whose primary purpose is to model the progression of accidents in light water reactor nuclear power plants. Major uses of MELCOR for nonreactor facilities include estimation of confinement behavior due to radiological source terms under postulated accident conditions (and their sensitivities and uncertainties in a variety of applications), evaluation of leak path factors, and survivability of fans, filters, and other Engineering Safety Features (ESFs).

For more information on MELCOR go to:

The MELCOR code-specific guidance report has been issued identifying applicable regimes in accident analysis, default inputs, and special conditions for using the code.

The MELCOR gap analysis was performed to determine the actions needed to bring the code into compliance with SQA criteria.