書誌事項
- タイトル別名
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- B205 Engineering study of gas flow in breeder pebble bed for fusion blanket
抄録
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.
収録刊行物
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- 動力・エネルギー技術の最前線講演論文集 : シンポジウム
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動力・エネルギー技術の最前線講演論文集 : シンポジウム 2012.17 (0), 265-266, 2012
一般社団法人 日本機械学会
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詳細情報 詳細情報について
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- CRID
- 1390282680862579200
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- NII論文ID
- 110009919685
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- ISSN
- 24242950
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- 本文言語コード
- ja
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- データソース種別
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- JaLC
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可