Modelling of natural convection processes during degraded core accidents
Conference
·
OSTI ID:5050674
This paper describes a model which has been developed to provide a parametric framework for characterizations of flow and heat transfer regimes in the uncovered region of the reactor core and the upper plenum of a pressurized water reactor (PWR) vessel following severe accidents. The reactor vessel is considered to be an anisotropic porous medium. The flow is modeled using the Brinkman-Forchheimer extended Darcy equations. The governing equations are solved with the SIMPLER algorithm and good agreement with previously reported numerical and experimental results is found. A parametric study is performed to investigate the influence of various dimensionless groups of the problem on the flow redistribution processes.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5050674
- Report Number(s):
- BNL-NUREG-40790; CONF-880724-11; ON: DE88007031
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
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HEAT TRANSFER
MASS TRANSFER
MATHEMATICAL MODELS
NATURAL CONVECTION
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REACTOR ACCIDENTS
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WATER MODERATED REACTORS