Heat flux distribution from a volumetrically heated pool with high Rayleigh number
- 1. Nuclear Power Engineering, IVO International Ltd, FIN-01019 IVO (Finland)
- 2. Power Plant Laboratory, Imatran Voima Oy, FIN-00019 IVO (Finland)
- 3. Department of Chemical and Nuclear Engineering, University of California, Santa Barbara, CA 93106 (United States)
Description
Experimental results are presented on the heat flux distribution at the boundaries of volumetrically heated pools at high enough Rayleigh numbers to be directly relevant to the problem of retention of a molten corium pool inside the lower head of a reactor pressure vessel. The experimental facility, named COPO, is a 2-dimensional ''slice'', Joule-heated and geometrically similar in shape (torispherical at 1/2-scale) to the lower head of a VVER-440 reactor. The results show that: the heat flux on the side wall (vertical portion) is essentially uniform; the downward heat flux strongly depends on position along the curved wall; and average fluxes on the side in the downward direction are in agreement with existing correlations, but somewhat underestimated in the upward direction. For the shape considered, the heat flux along the lower curved wall seems to be independent of the presence and extent of the liquid pool (contained by the vertical sidewalls) portion above it. ((orig.))
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 149
- Journal Issue
- 1-3
- Journal Page Range
- p. 401-408.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 6. international topical meeting on nuclear reactor thermal hydraulics (Nureth-6).
- Dates
- 5-8 Oct 1993.
- Place
- Grenoble (France).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 26016942
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT FLUX; HEAT TRANSFER; MELTDOWN; NUSSELT NUMBER; PRESSURE VESSELS; REACTOR EXPERIMENTAL FACILITIES; SIMULATION; SPATIAL DISTRIBUTION; WWER-3 REACTOR
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DISTRIBUTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS