Preliminary results of the TRAN experiment B-1 (annular channel)
Conference
·
OSTI ID:6059208
The current safety case for CRBR assumes that molten fuel will penetrate long distances through steel structures (such as the gaps between subassembly can walls in the axial and radial blankets), thus removing fuel and mitigating or terminating the accident. This process involves freezing of molten core materials on flat surfaces and curved surfaces of positive and negative curvature. Phenomenological data have been obtained on the freezing of thermite simulant in pin-bundle geometries and in tubes, and on the freezing of pure UO/sub 2/ in tubes. There is reason to believe that fuel crusts will be more stable in tubes because the tube wall holds the crust in compression. On the other hand, in flat-plate geometry or on the outside of fuel pins, the crust may not be stable since it is not in compression.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA); Science Applications, Inc., Albuquerque, NM (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6059208
- Report Number(s):
- SAND-83-1403C; CONF-831047-5; ON: DE83013981
- Country of Publication:
- United States
- Language:
- English
Similar Records
TRAN B-3: experimental investigation of fuel crust stability on melting surfaces of an annular flow channel
TRAN B-1: experimental investigation of fuel crust stability on surfaces of an annular flow channel. [LMFBR]
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Technical Report
·
Thu Jan 31 23:00:00 EST 1985
·
OSTI ID:5573289
TRAN B-1: experimental investigation of fuel crust stability on surfaces of an annular flow channel. [LMFBR]
Technical Report
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:5222194
TRAN B-2: the effect of low steel content on fuel penetration in a non-melting cylindrical flow channel
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·
Thu Jan 31 23:00:00 EST 1985
·
OSTI ID:5918691
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
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CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
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CORROSION RESISTANT ALLOYS
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FLUID MECHANICS
FUEL ASSEMBLIES
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HEAT RESISTING ALLOYS
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HYDRAULICS
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LIQUID METAL COOLED REACTORS
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MECHANICS
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MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
POWER REACTORS
REACTOR ACCIDENTS
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REACTOR SAFETY
REACTORS
SAFETY
SODIUM COOLED REACTORS
SOLIDIFICATION
STAINLESS STEEL-316
STAINLESS STEELS
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URANIUM DIOXIDE
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210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CLINCH RIVER BREEDER REACTOR
COMPUTER CALCULATIONS
CORIUM
CORROSION RESISTANT ALLOYS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICS
MELTDOWN
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
SODIUM COOLED REACTORS
SOLIDIFICATION
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TEST FACILITIES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES