Relocation and freezing of liquefied fuel-rod material. [PWR]
Severe degraded core cooling accidents, such as occurred at TMI-2 can potentially reach temperatures in excess of cladding melting. When the molten cladding is in contact with UO/sub 2/ fuel, the UO/sub 2/ will be dissolved contributing significantly to the total amount of liquefied material flowing down the rod and eventually freezing in a lower, cooler region of the core. The primary objectives of this paper are to evaluate the relocation and freezing characteristics of liquefied fuel rod material over a wide range of system conditions, physical characteristics of the fuel rod and liquefied material, and material thermo-physical properties to determine the relative influence of the controlling parameters. First the analytical model used in the analysis is briefly reviewed. The results of the analyses are then presented and discussed, and this is followed by the conclusions.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 7094067
- Report Number(s):
- EGG-M-04982; CONF-820717-4; ON: DE83000557
- Resource Relation:
- Conference: PAHR information exchange conference, Karlsruhe, F.R. Germany, 28 Jul 1982; Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MELTDOWN
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
CORIUM
LIQUID FLOW
REACTOR SAFETY
SOLIDIFICATION
URANIUM DIOXIDE
ZIRCONIUM OXIDES
ACCIDENTS
ACTINIDE COMPOUNDS
CHALCOGENIDES
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
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OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
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REACTORS
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TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM COMPOUNDS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled