Published September 1994 | Version v1
Journal article

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).