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Current Central Registry Toolbox Version(s): MELCOR 1.8.5
Code Owner: Sandia National Laboratory (SNL)

Description: MELCOR 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).

In May 2004, the DOE performed an evaluation of MELCOR against DOE’s safety software quality assurance criteria. A gap analysis report was generated that identifies the strengths and weaknesses based upon ASME NQA-1 criteria. Upon completion of this evaluation, MELCOR V1.8.5 was included in DOE’s safety software Central Registry as a safety analysis toolbox code.

For more information on MELCOR go to:

Reports and Publications Related to MELCOR:

Note: Non-DOE issued reports and publications are not endorsed for technical content by DOE. These reports are provided on this website as a courtesy to the DOE community.

The MELCOR code-specific guidance report has been issued identifying applicable regimes in accident analysis, default inputs, and special conditions for using the code, May 2004.

The MELCOR gap analysis was performed to determine the actions needed to bring the code into compliance with SQA criteria, May 2004.