Numerical Analysis of Lead-Bismuth-Water Direct Contact Boiling Heat Transfer
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概要
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Direct contact boiling heat transfer of sub-cooled water with lead-bismuth eutectic (Pb-Bi) was investigated for the evaluation of the performance of steam generation in direct contact of feed water with primary Pb-Bi coolant in upper plenum above the core in Pb-Bi-cooled direct contact boiling water fast reactor. An analytical two-fluid model was developed to estimate the heat transfer numerically. Numerical results were compared with experimental ones for verification of the model. The overall volumetric heat transfer coefficient was calculated from heat exchange rate in the chimney. It was confirmed that the calculated results agreed well with the experimental result.
- 一般社団法人 日本機械学会の論文
著者
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Takahashi Minoru
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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YAMADA Yumi
Department of Nuclear Engineering, Tokyo Institute of Technology
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