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DOE OSTI · 1813675

MELCOR

Dodge, Haley
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Abstract

MELCOR is a fully integrated, engineering-level computer code for modeling the progression of severe accidents in light water reactors (LWR) at nuclear power plants and nuclear fuel cycle facilities. Originally developed to assess severe accidents following Three Mile Island, MELCOR’s flexible modeling framework has enabled it to be applied to safety assessments of a much broader range of nuclear power reactor designs and other types of nuclear facilities processing radioactive material. Further, MELCOR can model a broad spectrum of severe accident phenomena such as thermal-hydraulic response in a reactor coolant system; core heat-up, degradation, and relocation; and transport behavior in both boiling water and pressurized water reactors.

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22 GENERAL STUDIES OF NUCLEAR REACTORS97 MATHEMATICS AND COMPUTING

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BibTeXRIS

Dodge, Haley. 2021-08-17. MELCOR. https://doi.org/10.2172/1813675

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