B205 核融合ブランケットにおける増殖材充填体内のガス流動に関する工学的研究(OS9 熱・流動)

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  • B205 Engineering study of gas flow in breeder pebble bed for fusion blanket

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In the case of a water cooled ceramic breeder in a blanket of a nuclear fusion reactor, pebbles of a ceramic tritium breeder, Li_2TiO_3 are packed in a container constituted by a partition plate. Helium purge gas is applied as a transport fluid in a tritium recovery system. It is important to build database of a pressure drop as part of a design of the tritium recovery system with prediction of amount of tritium released by the breeder pebble. In this experimental study, the pressure drops of helium purge gas through pebble bed were measured within the wide range of a flow rate up to 100 L/min. The experimental results indicate that a laminar flow is dominant and the pressure drop was correctly predicted by the empirical equation within a part of flow rate. Reliability of prediction ability of pressure drop was validated by this experiment within the flow rate which is less than 60 L/min and also less than 7.1 of the Reynolds number normalized by the pebble-diameter. Moreover, this paper describes that slight difference between the experimental result and the empirical equation within a range of flow rate from 60 L/min to 100 L/min.

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