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The Accomplishments of Lithium Target and Test Facility Validation Activities in the IFMIF/EVEDA Phase
https://repo.qst.go.jp/records/48900
https://repo.qst.go.jp/records/489001685a73e-cb6e-4405-b8b6-e2d07d5b008f
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-05-08 | |||||
| タイトル | ||||||
| タイトル | The Accomplishments of Lithium Target and Test Facility Validation Activities in the IFMIF/EVEDA Phase | |||||
| 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_6501 | |||||
| 資源タイプ | journal article | |||||
| 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 |
Arbeiter, Frederik
× Arbeiter, Frederik× Baluc, Nadine× Favuzza, Paolo× Gröschel, Friedrich× Heidinger, Roland× Ibarra, Angel× Knaster, Juan× Kanemura, Takuji× 近藤, 浩夫× Massaut, Vincent× Saverio, Nitti Francesco× Micciche, Gioacchino× 大平, 茂× Rapisarda, David× Sugimoto, Masayoshi× Wakai, Eiichi× Yokomine, Takehiko× 近藤 浩夫× 大平 茂 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | As part of the engineering validation and engineering design activities (EVEDA) phase for the international fusion materials irradiation facility IFMIF, major elements of a lithium target facility and the test facility were designed, prototyped and validated. For the lithium target facility, the EVEDA lithium test loop was built at JAEA and used to test the stability (waves and long term) of the lithium flow in the target, work out the startup procedures, and test lithium purification and analysis. It was confirmed by experiments in the Lifus 6 plant at ENEA that lithium corrosion on ferritic martensitic steels is acceptably low. Furthermore, complex remote handling procedures for the remote maintenance of the target in the test cell environment were successfully practiced. For the test facility, two variants of a high flux test module were prototyped and tested in helium loops, demonstrating their good capabilities of maintaining the material specimens at the desired temperature with a low temperature spread. Irradiation tests were performed for heated specimen capsules and irradiation instrumentation in the BR2 reactor at SCK-CEN. The small specimen test technique, essential for obtaining material test results with limited irradiation volume, was advanced by evaluating specimen shape and test technique influences. | |||||
| 書誌情報 |
Nuclear Fusion 巻 58, p. 015001-1-015001-6, 発行日 2018-05 |
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| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1088/1741-4326/aa8ba5/meta | |||||
