First in-core molten fuel pool experiment. [LMFBR]
If during a LMFBR accident a fuel debris bed is not adequately cooled by overlying sodium and dryout occurs, then the fuel would heat up and melt. Molten fuel pools are of concern due to their potential for ablation of the supporting structure and possible penetration of the reactor vessel. The major goal of the molten fuel pool program has been to develop a versatile experiment in which heat flux and structural ablation could be studied using real materials under typical temperature and heating conditions. This has now been accomplished, using the Annular Core Pulse Reactor (ACPR) to fission heat enriched UO/sub 2/. In the first experiment conducted, a small portion of a 0.834 kg UO/sub 2/ sample was melted, and temperature data were recorded to above the melting point of the UO/sub 2/ using ultrasonic thermometry.
- Research Organization:
- Sandia Labs., Albuquerque, N.Mex. (USA)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 5288159
- Report Number(s):
- SAND-77-1096C; CONF-771109-36
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
CONTAINERS
CORIUM
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MELTDOWN
MOCKUP
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
STRUCTURAL MODELS
TEST FACILITIES
TESTING
THORIUM COMPOUNDS
THORIUM OXIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES