MELCOR 1.8.2 assessment: The DF-4 BWR Damaged Fuel experiment
MELCOR is a fully integrated, engineering-level computer code being developed at Sandia National Laboratories for the USNRC, that models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs. As a part of an ongoing assessment, program, MELCOR has been used to model the ACRR in-pile DF-4 Damaged Fuel experiment. DF-4 provided data for early phase melt progression in BWR fuel assemblies, particularly for phenomena associated with eutectic interactions in the BWR control blade and zircaloy oxidation in the canister and cladding. MELCOR provided good agreement with experimental data in the key areas of eutectic material behavior and canister and cladding oxidation. Several shortcomings associated with the MELCOR modeling of BWR geometries were found and corrected. Twenty-five sensitivity studies were performed on COR, HS and CVH parameters. These studies showed that the new MELCOR eutectics model played an important role in predicting control blade behavior. These studies revealed slight time step dependence and no machine dependencies. Comparisons made with the results from four best-estimate codes showed that MELCOR did as well as these codes in matching DF-4 experimental data.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10110563
- Report Number(s):
- SAND--93-1377; ON: DE94004681
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
CORIUM
CORRECTIONS
EUTECTICS
EXPERIMENTAL DATA
FUEL ASSEMBLIES
FUEL-CLADDING INTERACTIONS
M CODES
MATHEMATICS AND COMPUTERS
MELTDOWN
OXIDATION
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
REACTOR SAFETY
SENSITIVITY ANALYSIS
ZIRCALOY