Thermal-Hydraulic Analysis for Inversely Stratified Molten Corium in Lower Vessel
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概要
- 論文の詳細を見る
The heat transfer of the inversely stratified molten corium in the lower vessel, which was experimentally demonstrated in the MASCA project, was analyzed. For the oxide layer, turbulent models of the k-ε and the large eddy simulation were examined through the CEA BALI test analysis, and the Mason-Derbyshire Smagorinsky large eddy simulation, which models the anisotropic buoyancy effect, was selected. A melt-solidification model was incorporated for the metal layer analysis since our preliminary analysis shows that the vessel boundary change due to its melting is important. An analysis under an inversely stratified configuration of a lower power density condition shows that the peak heat flux from the corium does not exceed the critical heat flux of the flooded vessel. However, the heat flux focuses at the top of the lower metal layer because it is under the thermally stable condition, and this focusing would be a new challenge for the in-vessel retention.
- 一般社団法人 日本原子力学会の論文
- 2008-09-01
著者
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SAITO Masaki
Tokyo institute of Technology
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Saito Masaki
Tokyo Institute Of Technol.
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FUKASAWA Masanori
Japan Nuclear Energy Safety Organization
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Hayakawa Satoshi
Mitsubishi Fbr Systems Inc.
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