LMFBR fuel analysis, Task B: post-accident heat removal. Final report, 1 Jul 1975--30 Sep 1976
Technical Report
·
OSTI ID:7308548
The behavior of molten core debris following a hypothetical core disruptive accident in the proposed Clinch River Breeder Reactor Plant is examined. 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). School of Engineering and Applied Science
- DOE Contract Number:
- AT(49-24)-0159
- OSTI ID:
- 7308548
- Report Number(s):
- PB-262407; UCLA-ENG-76115
- Country of Publication:
- United States
- Language:
- English
Similar Records
LMFBR fuel analysis. Task B. Post-accident heat removal. Final report, July 1, 1975--September 30, 1976
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LMFBR fuel analysis. Task B: Post-accident heat removal. Final report, October 1, 1976--September 30, 1977
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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
AFTER-HEAT REMOVAL
ALKALI METALS
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
CORE CATCHERS
CORIUM
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MELTDOWN
METALS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTORS
REMOVAL
SODIUM
SODIUM COOLED REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
ALKALI METALS
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
CORE CATCHERS
CORIUM
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MELTDOWN
METALS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTORS
REMOVAL
SODIUM
SODIUM COOLED REACTORS