MELCOR analysis of the TMI-2 accident
The MELCOR computer code has been used to analyze the first 174 minutes of the TMI-2 accident. MELCOR is being developed at Sandia National Laboratories for the US Nuclear Regulatory Commission for the purpose of analyzing severe accidents in nuclear power plants. Comparison of the code predictions to the available data shows that MELCOR is capable of modeling the key events of the TMI-2 accident and reasonable agreement with the available data is obtained. In particular, the core degradation and hydrogen generation models agree with best-estimate information available for this phase of the accident. While the code uses simplified modeling, all important characteristics of the reactor system and the accident phenomena could be modeled. This exercise demonstrates that MELCOR is applicable to severe accident analysis. 6 refs., 7 figs., 2 tabs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6877166
- Report Number(s):
- SAND-88-1258C; CONF-881024-4; ON: DE89001216
- Country of Publication:
- United States
- Language:
- English
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