LMFBR fuel analysis. Task B. Post-accident heat removal. Final report, July 1, 1975--September 30, 1976
The report deals with the behavior of molten core debris following a hypothetical core disruptive accident in the proposed Clinch River Breeder Reactor Plant. Heat dissipating characteristics of an ex-vessel sacrificial bed have been analyzed. A novel form of heat transfer, analogous to film boiling, has been proposed to describe heat transfer from a heat generating pool to surrounding steel walls. Bounding type heat transfer calculations are also made to quantify such hypothetical accident characteristics as debris bed remelting, debris bed dryout in sodium, and failure of the reactor cavity steel liner. Several documents that have been submitted to the NRC for its review of the CRBRP are discussed with attention being drawn to heat transfer related issues.
- Research Organization:
- California Univ., Los Angeles (USA)
- OSTI ID:
- 7110969
- Report Number(s):
- NUREG-0147; UCLA-ENG-76115
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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ACCIDENTS
AFTER-HEAT REMOVAL
BREEDER REACTORS
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ENERGY TRANSFER
EPITHERMAL REACTORS
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210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
AFTER-HEAT REMOVAL
BREEDER REACTORS
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ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
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RESEARCH PROGRAMS
SAFETY
SODIUM COOLED REACTORS