A direct comparison of MELCOR 1.8.3 and MAAP4 results for several PWR & BWR accident sequences
- ITS Corp. Albuquerque NM (United States)
- Sandia National Labs., Albuquerque, NM (United States)
- NUPEC, Minato-ku, Tokyo (Japan)
This paper presents a comparison of calculations of severe accident progression for several postulated accident sequences for representative Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) nuclear power plants performed with the MELCOR 1.8.3 and the MAAP4 computer codes. The PWR system examined in this study is a 1100 MWe system similar in design to a Westinghouse 3-loop plant with a large dry containment; the BWR is a 1100 MWe system similar in design to General Electric BWR/4 with a Mark I containment. A total of nine accident sequences were studied with both codes. Results of these calculations are compared to identify major differences in the timing of key events in the calculated accident progression or other important aspects of severe accident behavior, and to identify specific sources of the observed differences.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 288425
- Report Number(s):
- SAND--96-2053C; CONF-960912--29; ON: DE96014078
- Country of Publication:
- United States
- Language:
- English
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