LMFBR fuel analysis. Task B. Post-accident heat removal. Final report, July 1, 1975--September 30, 1976
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 79 p.
- Report number
- NUREG--0147
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8334958
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- AFTER-HEAT REMOVAL; CLINCH RIVER BREEDER REACTOR; HEAT TRANSFER; LMFBR TYPE REACTORS; REACTOR CORE DISRUPTION; REACTOR SAFETY; RESEARCH PROGRAMS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SODIUM COOLED REACTORS
Optional Information
- Secondary number(s)
- UCLA-ENG--76115.