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Conceptual Design for Higher Capability of the Tritium Production by the Honeycomb Structure Blanket of JA DEMO
https://repo.qst.go.jp/records/76991
https://repo.qst.go.jp/records/76991a33470f5-71c0-49d2-b50e-21b4ed4a698e
Item type | 会議発表用資料 / Presentation(1) | |||||
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公開日 | 2019-09-30 | |||||
タイトル | ||||||
タイトル | Conceptual Design for Higher Capability of the Tritium Production by the Honeycomb Structure Blanket of JA DEMO | |||||
言語 | ||||||
言語 | eng | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_c94f | |||||
資源タイプ | conference object | |||||
アクセス権 | ||||||
アクセス権 | metadata only access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
著者 |
Someya, Yoji
× Someya, Yoji× Tobita, Kenji× Hiwatari, Ryoji× Sakamoto, Yoshiteru× Someya, Yoji× Tobita, Kenji× Hiwatari, Ryoji× Sakamoto, Yoshiteru |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | The conceptual design of the breeding blanket with a honeycomb structure has been created with pressure tightness against in-box Loss-of-coolant accident based on a water-cooled solid breeder. In the previous design, the breeding area of the module was divided into 0.1-m-squared cells with rib structure. As a honeycomb structure is higher in pressure tightness than a square prism structure, the area for filling the mixed pebbles breeder of Li2TiO3 pebbles and Be12Ti ones can be enlarged. Then, the overall TBR is improved to increase the packing ratio of the tritium breeding material. In the created blanket, the capabilities of the pressure tightness, tritium breeding and heat removal are studied using interaction analyses of the neutronics, stresses and fluid dynamics analysis. As a result, a rib with the thickness of 0.015 m is needed to withstand the design pressure of 17.2 MPa by a stress analysis. The packing factor of the mixed pebbles breeder increase to 77 % from 68 % by changing the rib structure from a square prism structure to a honeycomb structure. From the 3D neutronics analysis results, the target of the overall TBR (>1.05) is achievable. The cooling system for the created blanket is designed by fluid dynamics analysis based on the PWR water conditions which are the coolant temperature of 290 - 325 ºC and the operation pressure of 15.5 MPa, respectively. In addition, the tritium extraction system in the created blanket is proposed together with the purge gas system which does not clog the holes. The saturated time of the tritium extraction is also estimated to grasp the tritium inventory in the breeding area. |
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会議概要(会議名, 開催地, 会期, 主催者等) | ||||||
内容記述タイプ | Other | |||||
内容記述 | 14th International Symposium on Fusion Nuclear Technology (ISFNT-14) | |||||
発表年月日 | ||||||
日付 | 2019-09-25 | |||||
日付タイプ | Issued |