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j.ijhydene.2021.11.225.pdf | 2.29 MB | Adobe PDF | 見る/開く |
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DCフィールド | 値 | 言語 |
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dc.contributor.author | Mukai, Keisuke | en |
dc.contributor.author | Kenjo, Shunsuke | en |
dc.contributor.author | Iwamatsu, Naoto | en |
dc.contributor.author | Mahmoud, Bakr | en |
dc.contributor.author | Chikada, Takumi | en |
dc.contributor.author | Yagi, Juro | en |
dc.contributor.author | Konishi, Satoshi | en |
dc.contributor.alternative | 向井, 啓祐 | ja |
dc.contributor.alternative | 見城, 俊介 | ja |
dc.contributor.alternative | 岩松, 尚杜 | ja |
dc.contributor.alternative | 八木, 重郎 | ja |
dc.contributor.alternative | 小西, 哲之 | ja |
dc.date.accessioned | 2022-01-31T00:10:13Z | - |
dc.date.available | 2022-01-31T00:10:13Z | - |
dc.date.issued | 2022-01 | - |
dc.identifier.uri | http://hdl.handle.net/2433/267732 | - |
dc.description.abstract | Understanding the permeation behavior of tritium from a pebble bed breeding blanket is essential for establishing a self-sufficient fuel cycle in a nuclear fusion reactor. It is known that double corrosion layers forms on reduced activation ferritic-martensitic (RAFM) steel surface by gas release from a ceramic breeder material, however, its effect on hydrogen permeation behavior has not been elucidated. Herein, in-situ measurement of hydrogen permeation through an F82H RAFM wall of a ceramic breeder pebble bed was performed under H₂-added sweep gas conditions. The corrosion layer formed on the F82H sample had a dense microstructure, which reduced hydrogen permeation flux at least by one order of magnitude. The permeation reduction factors were 20–50 at the water-coolant temperature of a blanket. A self-repairing ability is expected for the surface oxide layer as the corrosion occurs spontaneously inside a breeding blanket. | en |
dc.language.iso | eng | - |
dc.publisher | Elsevier BV | en |
dc.rights | © 2021. This manuscript version is made available under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International license. | en |
dc.rights | The full-text file will be made open to the public on 29 January 2024 in accordance with publisher's 'Terms and Conditions for Self-Archiving'. | en |
dc.rights | This is not the published version. Please cite only the published version. この論文は出版社版でありません。引用の際には出版社版をご確認ご利用ください。 | en |
dc.rights.uri | https://creativecommons.org/licenses/by-nc-nd/4.0/ | - |
dc.subject | Tritium permeation | en |
dc.subject | Chemical compatibility | en |
dc.subject | Nuclear fusion | en |
dc.subject | Breeding blanket | en |
dc.subject | Reduced activation ferritic martensitic steel | en |
dc.title | Hydrogen permeation from F82H wall of ceramic breeder pebble bed: The effect of surface corrosion | en |
dc.type | journal article | - |
dc.type.niitype | Journal Article | - |
dc.identifier.jtitle | International Journal of Hydrogen Energy | en |
dc.identifier.volume | 47 | - |
dc.identifier.issue | 9 | - |
dc.identifier.spage | 6154 | - |
dc.identifier.epage | 6163 | - |
dc.relation.doi | 10.1016/j.ijhydene.2021.11.225 | - |
dc.textversion | author | - |
dcterms.accessRights | embargoed access | - |
datacite.date.available | 2024-01-29 | - |
datacite.awardNumber | 19H01873 | - |
datacite.awardNumber | 20K14442 | - |
datacite.awardNumber.uri | https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-19H01873/ | - |
datacite.awardNumber.uri | https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-20K14442/ | - |
dc.identifier.pissn | 0360-3199 | - |
jpcoar.funderName | 日本学術振興会 | ja |
jpcoar.funderName | 日本学術振興会 | ja |
jpcoar.awardTitle | 核融合炉ブランケットにおける水素・腐食・照射相乗効果の解明と機能性材料設計 | ja |
jpcoar.awardTitle | 核融合ブランケットの中性子輸送と燃料生産性の実験評価 | ja |
出現コレクション: | 学術雑誌掲載論文等 |
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