Cooling of particulate debris beds: analysis of the initial D-series experiments. [LMFBR]
Conference
·
OSTI ID:6494138
In an effort to provide basic data on the cooling of fast reactor debris, three in-pile experiments employing oxide fuel particulate in liquid sodium were completed in late 1977. Preliminary results from these experiments were reported shortly after their completion at the Third Post-Accident Heat Removal Information Exchange, at Argonne National Laboratory. In these experiments, a distribution of 100 ..mu..m to 1000 ..mu..m-sized particles of enriched UO/sub 2/ was fission-heated to simulate decay-heated debris. In each experiment, the UO/sub 2/ particles were contained in a closed, flat-bottomed vessel 012 mm in diameter which was insulated on the diameter and bottom. Sufficient sodium was included to saturate the bed of particles and to provide a volume of bulk sodium above the bed at a controlled temperature. Parameters of interest in the experiments are given.
- Research Organization:
- Sandia Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 6494138
- Report Number(s):
- SAND-78-1754C; CONF-781079-1
- Country of Publication:
- United States
- Language:
- English
Similar Records
Preliminary results from initial in-pile debris bed experiments. [LMFBR]
Postaccident heat removal: debris-bed experiments D-2 and D-3. [LMFBR]
Debris bed studies and experiments at Sandia Laboratories. [LMFBR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:5197687
Postaccident heat removal: debris-bed experiments D-2 and D-3. [LMFBR]
Technical Report
·
Tue Aug 01 00:00:00 EDT 1978
·
OSTI ID:6494241
Debris bed studies and experiments at Sandia Laboratories. [LMFBR]
Technical Report
·
Sat Jul 01 00:00:00 EDT 1978
·
OSTI ID:6633471
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
AFTER-HEAT REMOVAL
BREEDER REACTORS
CHALCOGENIDES
DRYOUT
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
HEAT TRANSFER
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTORS
REMOVAL
TEMPERATURE GRADIENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
AFTER-HEAT REMOVAL
BREEDER REACTORS
CHALCOGENIDES
DRYOUT
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
HEAT TRANSFER
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTORS
REMOVAL
TEMPERATURE GRADIENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES