MELCOR 1.8.2 calculations of selected sequences for the ABWR
This report summarizes the results from MELCOR calculations of severe accident sequences in the ABWR and presents comparisons with MAAP calculations for the same sequences. MELCOR was run for two low-pressure and three high-pressure sequences to identify the materials which enter containment and are available for release to the environment (source terms), to study the potential effects of core-concrete interaction, and to obtain event timings during each sequence; the source terms include fission products and other materials such as those generated by core-concrete interactions. Sensitivity studies were done on the impact of assuming limestone rather than basaltic concrete and on the effect of quenching core debris in the cavity compared to having hot, unquenched debris present.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10177514
- Report Number(s):
- SAND-94-0938; ON: DE94017783; BR: GB0103012; TRN: 94:020110
- Resource Relation:
- Other Information: PBD: Jul 1994
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR ACCIDENTS
SOURCE TERMS
CONCRETES
INTERACTIONS
CORIUM
M CODES
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
FISSION PRODUCT RELEASE
CONTAINMENT
COMPUTER CALCULATIONS
220900
220502
210100
RADIOACTIVE EFFLUENTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED