DC-1 and DC-2 debris coolability and melt dynamics experiments
Technical Report
·
OSTI ID:5507258
The DC experiment series investigates the heatup and melt of dry reactor core debris through nuclear heating of actual reactor materials in order to obtain the thermal properties of dry debris, the nature of the transition from a debris bed to a molten pool, and the thermal and kinetic behavior of molten pools. The purpose is to develop a data base in support of model development. This report provides a description of the two experiments in the DC series and documents the configuration and the data. These tests investigated dry debris beds (approx.2 kg) composed of pure UO/sub 2/ and mixed UO/sub 2/ and stainless steel. Heat transfer characteristics were studied at several steady-state conditions below melt. The beds were then taken into melt to observe the growth of a molten pool in the UO/sub 2/ bed and the agglomeration and migration of steel in a composite bed. The peak measured temperature in the UO/sub 2/ bed above 3000/sup 0/C. Approximately 50% of the urania formed a molten pool. In the mixed UO/sub 2/ and steel bed, the peak measured temperature was 2600/sup 0/C. With about 90% of the steel molten, material migration occurred resulting in a significant increase in the gross bed thermal conductivity.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5507258
- Report Number(s):
- NUREG/CR-4060; SAND-84-1367; ON: TI85016047
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CHROMIUM ALLOYS
COOLING
CORIUM
CORROSION RESISTANT ALLOYS
DISPERSIONS
ENERGY TRANSFER
HEAT TRANSFER
IRON ALLOYS
IRON BASE ALLOYS
MELTDOWN
MIXTURES
OXIDES
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
STAINLESS STEELS
STEELS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CHROMIUM ALLOYS
COOLING
CORIUM
CORROSION RESISTANT ALLOYS
DISPERSIONS
ENERGY TRANSFER
HEAT TRANSFER
IRON ALLOYS
IRON BASE ALLOYS
MELTDOWN
MIXTURES
OXIDES
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
STAINLESS STEELS
STEELS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES