| アイテムタイプ |
学術雑誌論文 / Journal Article(1) |
| 公開日 |
2024-03-01 |
| タイトル |
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タイトル |
IFMIF/EVEDA achievements overview |
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言語 |
en |
| 言語 |
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|
言語 |
eng |
| 資源タイプ |
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|
資源タイプ識別子 |
http://purl.org/coar/resource_type/c_6501 |
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資源タイプ |
journal article |
| 著者 |
Yann Carin
Sugimoto Masayoshi
Herve Dzitko
Hasegawa Kazuo
Dominique Gex
Kondo Keitaro
Stephane Chel
Alberto Facco
David Jimenez-Rey
Kasugai Atsushi
Philippe Cara
Gioacchino Micciche
Andrea Pisent
Dirk Radloff
Dmitry Terentyev
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| 抄録 |
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内容記述タイプ |
Abstract |
|
内容記述 |
In a fusion reactor, the plasma based on a deuterium-tritium reaction generates high energy neutron flux interacting with the materials of the plasma facing components. In order to study the irradiated behavior of these materials, the International Fusion Materials Irradiation Facility (IFMIF) was conceived to generate these fusion relevant neutrons through d-Li stripping source. IFMIF is presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the Broader Approach agreement signed between EURATOM and Japanese Government in 2007. This agreement mandates the IFMIF/EVEDA project to validate the design of the different systems of IFMIF and to produce an integrated engineering design of IFMIF, together with the data necessary for future decisions on its construction and operation. While the Engineering Validation Activity (EVA) of the Lithium Target Facility and the Test Facility was completed by constructing prototypes, the EVA of the Accelerator Facility with the Linear IFMIF Prototype Accelerator (LIPAc) is still on-going at the Rokkasho Fusion Institute, Japan. This paper overviews the achievements in the previous phase ended on 31 March 2020 and the progress in the current phase to complete the commissioning of the LIPAc. |
| 書誌情報 |
Fusion Engineering and Design
巻 201,
p. 114258,
発行日 2024-04
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| 出版者 |
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出版者 |
Elsevier B.V. |
| DOI |
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識別子タイプ |
DOI |
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関連識別子 |
https://doi.org/10.1016/j.fusengdes.2024.114258 |
