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Interface temperature between solid and liquid corium in severe accident situations: A comprehensive study of characteristic time delay needed for reaching liquidus temperature

T liquidus was proposed as the interface temperature ( Seiler and Froment, 2000), for various severe accident situations for thermalhydraulic steady state. This proposal was made on the basis of the analysis of solidification front stability in thermalhydraulic steady state for volumetrically heated...

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Published in:Nuclear engineering and design 2010-08, Vol.240 (8), p.1975-1985
Main Authors: Combeau, H., Appolaire, B., Seiler, J.M.
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Language:English
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cited_by cdi_FETCH-LOGICAL-c377t-144c0ad337a84dd3ad0baec66c54b0307a388a6f41accc02b740b7678047fdcb3
cites cdi_FETCH-LOGICAL-c377t-144c0ad337a84dd3ad0baec66c54b0307a388a6f41accc02b740b7678047fdcb3
container_end_page 1985
container_issue 8
container_start_page 1975
container_title Nuclear engineering and design
container_volume 240
creator Combeau, H.
Appolaire, B.
Seiler, J.M.
description T liquidus was proposed as the interface temperature ( Seiler and Froment, 2000), for various severe accident situations for thermalhydraulic steady state. This proposal was made on the basis of the analysis of solidification front stability in thermalhydraulic steady state for volumetrically heated corium pools and was extended to reactor transients with slow solidification rates that are controlled by the long-term decrease in residual power. The conclusions were corroborated by prototypic corium and variable solidification rates obtained by experimental approaches ( Dauvois et al., 2000; Journeau et al., 2003) for corium containing small amounts of silica or none at all. When the concentration in silica increases (approximately above 10 wt%), it was concluded from the experiments that a plane-front situation could not be obtained. The present work offers a theoretical approach to the maximum time delay that is necessary for mass transfer and full phase-segregation in volumetrically heated liquid pools bounded by a crust. It is concluded that full segregation is obtained for in-vessel situations within time delays that are shorter or of the same order of magnitude as the characteristic time for the corium pool to form and evolve to a quasi-steady-state situation. The characteristic time delay for mass transfer associated with simulant material experiments is also determined. Phase segregation can also be obtained for corium–concrete interaction, provided that the silica content is less than approximately 10 wt%. However in the latter case, more complex phenomena occur at the interface due to the interaction with sparging gas (such as porous medium formation) which requires a different model approach.
doi_str_mv 10.1016/j.nucengdes.2010.04.004
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source ScienceDirect Freedom Collection 2022-2024
subjects Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Fuels
Installations for energy generation and conversion: thermal and electrical energy
Mass transfer
Nuclear fuels
Nuclear power generation
Nuclear reactor components
Pools
Segregations
Silicon dioxide
Solidification
Time delay
title Interface temperature between solid and liquid corium in severe accident situations: A comprehensive study of characteristic time delay needed for reaching liquidus temperature
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