Analyses of Mark I drywell shell melt-through
Conference
·
OSTI ID:6815304
A series of parametric calculations of the thermal attack of molten corium on a steel shell have been performed with the TAC2D computer code in order to elucidate uncertainties about the survivability of the BWR Mark I containment boundary in the event of a core-melt accident. Since TAC2D is a two-dimensional, fixed geometry heat transfer code, it is not possible to capture some of the complexities of the debris-concrete interactions which would occur in this accident. However, the two-dimensional transient nature of the thermal attack is modeled better with TAC2D than is possible with existing debris-concrete interaction codes. The calculations consist of two base cases (one with overlying water and one without) and numerous sensitivity variations about each case. The study is not intended as an uncertainty assessment per se. Rather,it is intended that the results can be combined with assessments of the parameter ranges to assist in the estimation of overall uncertainty about the drywell shell melt-through issue. Sensitivities investigated include mixed versus layered debris, heat transfer parameters, initial corium temperature, chemical heating rate, heat transfer conditions in the gap outside the shell, and corium depth. All but two of the cases resulted in ablation and melt-through of the shell in times that ranged from 8.3 minutes to 75.8 minutes. The two cases that did not melt both involved the mixed debris assumption and enhanced boiling heat transfer to an overlying water pool. 13 refs., 14 figs., 3 tabs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6815304
- Report Number(s):
- SAND-88-2282C; CONF-881169-1; ON: DE88016343
- Country of Publication:
- United States
- Language:
- English
Similar Records
TAC2D studies of Mark I contaiment drywell shell melt-through
Analyses of Mark I drywell shell melt-through
Impact of core-concrete interactions in the Mark I containment drywell on containment integrity and failure of the drywell liner
Technical Report
·
Mon Aug 01 00:00:00 EDT 1988
·
OSTI ID:6913288
Analyses of Mark I drywell shell melt-through
Conference
·
Thu Dec 31 23:00:00 EST 1987
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5957318
Impact of core-concrete interactions in the Mark I containment drywell on containment integrity and failure of the drywell liner
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:6476557
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FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
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NUMERICAL DATA
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
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TWO-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS