Molten fuel radial motion during a high temperature transient in LWRS
Description
Molten fuel radial motion during a high temperature transient is of interest to current light water reactor (LWR) safety analyses. Particularly, since partial or complete melting of the zircaloy cladding may occur upon the cladding being contacted by molten UO2-fuel, because of the large difference between the melting point of the fuel and that of the cladding. During a high temperature transient, fuel melting may be initiated at the center of the rods and propagate radially outwards. Fuel cracking, which usually occurs along radial and horizontal planes in the fuel pellet during reactor normal operation provides paths for such molten fuel to relocate outside the central melting zone. This paper presents an analytical study of the transient freezing of a superheated liquid that penetrates an initially empty crack maintained at a constant subfreezing temperature. Results of the analysis are applied to assess the molten UO2 fuel radial extrusion observed in some of the in-pile tests in which power-cooling-mismatch (PCM) conditions in a pressurized water reactor were simulated
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
11517532.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 5 p.
- Report number
- CONF-791103--26
Conference
- Title
- American Nuclear Society meeting.
- Dates
- 12 - 16 Nov 1979.
- Place
- San Francisco, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11517532
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FUEL-CLADDING INTERACTIONS; HYDRAULICS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION; TRANSIENTS; URANIUM DIOXIDE; ZIRCALOY
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; DISTRIBUTION; OXIDES; OXYGEN COMPOUNDS; REACTORS; SAFETY; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS