MELCOR analysis of the TMI-2 accident

Conference · Sun Dec 31 23:00:00 EST 1989

OSTI ID:6360144

Boucheron, E A

This paper describes the analysis of the Three Mile Island-2 (TMI-2) standard problem that was performed with MELCOR. The MELCOR computer code is being developed by Sandia National Laboratories for the Nuclear Regulatory Commission for the purpose of analyzing severe accident in nuclear power plants. The primary role of MELCOR is to provide realistic predictions of severe accident phenomena and the radiological source team. The analysis of the TMI-2 standard problem allowed for comparison of the model predictions in MELCOR to plant data and to the results of more mechanistic analyses. This exercise was, therefore valuable for verifying and assessing the models in the code. The major trends in the TMI-2 accident are reasonably well predicted with MELCOR, even with its simplified modeling. Comparison of the calculated and measured results is presented and, based on this comparison, conclusions can be drawn concerning the applicability of MELCOR to severe accident analysis. 5 refs., 10 figs., 3 tabs.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6360144
• Report Number(s): SAND-90-2580C; CONF-9010185--17; ON: DE91005862
• Country of Publication: United States
• Language: English

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