{"created":"2023-05-15T14:37:43.048995+00:00","id":48656,"links":{},"metadata":{"_buckets":{"deposit":"143f9827-4e26-4841-83de-582920ba2a1d"},"_deposit":{"created_by":1,"id":"48656","owners":[1],"pid":{"revision_id":0,"type":"depid","value":"48656"},"status":"published"},"_oai":{"id":"oai:repo.qst.go.jp:00048656","sets":["1"]},"author_link":["489385","489397","489403","489398","489400","489394","489395","489399","489387","489392","489401","489384","489389","489396","489388","489381","489393","489380","489386","489402","489390","489383","489391","489382"],"item_8_biblio_info_7":{"attribute_name":"書誌情報","attribute_value_mlt":[{"bibliographicIssueDates":{"bibliographicIssueDate":"2017-10","bibliographicIssueDateType":"Issued"},"bibliographicIssueNumber":"12","bibliographicPageEnd":"126050-12","bibliographicPageStart":"126050-1","bibliographicVolumeNumber":"57","bibliographic_titles":[{"bibliographic_title":"Nuclear Fusion"}]}]},"item_8_description_5":{"attribute_name":"抄録","attribute_value_mlt":[{"subitem_description":"Power exhaust to the divertor and the conceptual design have been investigated for a steady-state DEMO in Japan with 1.5 GW-level fusion power and the major radius of 8.5 m, where the plasma parameters were revised appropriate for the impurity seeding scenario. A system code survey for the Ar impurity seeding suggested the volume-averaged density, impurity concentration and exhaust power from the main plasma of Psep = 205-285 MW. The divertor plasma simulation (SONIC) was performed in the divertor leg length of 1.6 m with the fixed exhaust power to the edge of Pout = 250MW and the total radiation fraction at the edge, SOL and divertor (Prad/Pout = 0.8), as a first step to investigate appropriate design of the divertor size and geometry. At the outer target, partial detachment was produced near the strike-point, and the peak heat load (qtarget) at the attached region was reduced to ~5 MWm-2 with appropriate fuel and impurity puff rates. At the inner divertor target, full detachment of ion flux was produced and the peak qtarget was less than 10 MWm-2 mostly due to the surface-recombination. These results showed a power exhaust scenario and the divertor design concept. An integrated design of the water-cooling heat sink for the long leg divertor was proposed. Cu-ally (CuCrZr) cooling pipe was applicable as the heat sink to handle the high heat flux near the strike-point, where displacements per atom rate was estimated to be 0.5-1.5 per year by neutronics calculation. An arrangement of the coolant rooting for Cu-alloy and Reduced Activation Ferritic Martensitic (RAFM) steel (F82H) pipes in a divertor cassette was investigated, and the heat transport analysis of the W-monoblock and Cu-alloy pipe under the peak qtarget of 10 MWm-2 and nuclear heating was performed. The maximum temperatures on the W-surface and Cu-alloy pipe were 1021 and 331C. Heat flux of 16 MWm-2 was distributed in the major part of the coolant pipe. These results were acceptable for the plasma facing and structural materials. ","subitem_description_type":"Abstract"}]},"item_8_publisher_8":{"attribute_name":"出版者","attribute_value_mlt":[{"subitem_publisher":"IOP Publishing"}]},"item_8_relation_14":{"attribute_name":"DOI","attribute_value_mlt":[{"subitem_relation_type_id":{"subitem_relation_type_id_text":"10.1088/1741-4326/aa867a","subitem_relation_type_select":"DOI"}}]},"item_8_relation_17":{"attribute_name":"関連サイト","attribute_value_mlt":[{"subitem_relation_name":[{"subitem_relation_name_text":"https://doi.org/10.1088/1741-4326/aa867a"}],"subitem_relation_type_id":{"subitem_relation_type_id_text":"https://doi.org/10.1088/1741-4326/aa867a","subitem_relation_type_select":"DOI"}}]},"item_access_right":{"attribute_name":"アクセス権","attribute_value_mlt":[{"subitem_access_right":"metadata only access","subitem_access_right_uri":"http://purl.org/coar/access_right/c_14cb"}]},"item_creator":{"attribute_name":"著者","attribute_type":"creator","attribute_value_mlt":[{"creatorNames":[{"creatorName":"朝倉, 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宜照","creatorNameLang":"en"}],"nameIdentifiers":[{"nameIdentifier":"489401","nameIdentifierScheme":"WEKO"}]},{"creatorNames":[{"creatorName":"日渡 良爾","creatorNameLang":"en"}],"nameIdentifiers":[{"nameIdentifier":"489402","nameIdentifierScheme":"WEKO"}]},{"creatorNames":[{"creatorName":"飛田 健次","creatorNameLang":"en"}],"nameIdentifiers":[{"nameIdentifier":"489403","nameIdentifierScheme":"WEKO"}]}]},"item_language":{"attribute_name":"言語","attribute_value_mlt":[{"subitem_language":"eng"}]},"item_resource_type":{"attribute_name":"資源タイプ","attribute_value_mlt":[{"resourcetype":"journal article","resourceuri":"http://purl.org/coar/resource_type/c_6501"}]},"item_title":"Studies of Power Exhaust and Divertor Design for a 1.5 GW-level Fusion Power DEMO ","item_titles":{"attribute_name":"タイトル","attribute_value_mlt":[{"subitem_title":"Studies of Power Exhaust and Divertor Design for a 1.5 GW-level Fusion Power DEMO "}]},"item_type_id":"8","owner":"1","path":["1"],"pubdate":{"attribute_name":"公開日","attribute_value":"2018-03-28"},"publish_date":"2018-03-28","publish_status":"0","recid":"48656","relation_version_is_last":true,"title":["Studies of Power Exhaust and Divertor Design for a 1.5 GW-level Fusion Power DEMO "],"weko_creator_id":"1","weko_shared_id":-1},"updated":"2023-05-15T23:25:45.068809+00:00"}