Assessment of LWR fuel foaming potential during core meltdown accidents
- 1. Engineering Science and Analysis, Idaho Falls, ID
Description
Fuel melting in severe core damage accidents will lead to the rapid release of fission gas from the fuel matrix and the volatilization of low boiling point metallic inclusions, which can be expected to significantly influence molten fuel dynamics. A quantitative analysis of UO2 foaming potential is presented here based upon an assessment of the time characteristics for bubble growth, surface escape, film thinning, and bubble coalescence. Analysis indicates that although the potential exists for early molten UO2 foaming, such foams are basically unstable and tend to collapse, thereby releasing volatilized fission products from the molten fuel debris. Release of such fission products will impact radiological source term evaluation and can result in up to a 40-percent reduction in the residual decay heat within the core debris
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 2
- Journal Page Range
- p. 1409-1420.
- Report number
- NUREG/CP--0027-Vol.2
Conference
- Title
- International meeting on thermal nuclear reactor safety (ANS topical meeting).
- Dates
- 29 Aug - 2 Sep 1982.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14792452
- 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
- AFTER-HEAT; BUBBLES; BWR TYPE REACTORS; FISSION PRODUCT RELEASE; FOAMS; HYDRODYNAMICS; MELTDOWN; PWR TYPE REACTORS; REACTOR SAFETY; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; COLLOIDS; DISPERSIONS; FLUID MECHANICS; MECHANICS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTORS; SAFETY; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS