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Dust Generation in Tokamaks: Overview of Beryllium and Tungsten Dust Characterisation in JET with the ITER-Like Wall
https://repo.qst.go.jp/records/49589
https://repo.qst.go.jp/records/4958910f6f830-494c-4d20-a6dc-65c95ba7fabd
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2019-02-10 | |||||
| タイトル | ||||||
| タイトル | Dust Generation in Tokamaks: Overview of Beryllium and Tungsten Dust Characterisation in JET with the ITER-Like Wall | |||||
| 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 |
M., Rubel (Royal Institute of Technology, Sweden)
× M., Rubel (Royal Institute of Technology, Sweden)× A., Widdowson (Culham Centre for Fusion Energy, UK)× J., Grzonka (Warsaw University of Technology, Poland)× E., Fortuna-Zalesna (Warsaw University of Technology, Poland)× Sunwoo, Moon (Royal Institute of Technology, Sweden)× P., Petersson (Royal Institute of Technology, Sweden)× N., Ashikawa (National Institute for Fusion Science)× Asakura, Nobuyuki× Hamaguchi, Dai× Y., Hatano (Toyama University)× Isobe, Kanetsugu× S., Masuzaki (National Institute for Fusion Science)× Kurotaki, Hironori× Y., Oya (Shizuoka University)× Oyaizu, Makoto× M., Tokitani (National Institute for Fusion Science)× Contributors, JET× Asakura, Nobuyuki× Hamaguchi, Dai× Isobe, Kanetsugu× Kurotaki, Hironori× Oyaizu, Makoto |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Operation of the JET tokamak with beryllium and tungsten ITER-like wall provides unique opportunity for detailed studies on dust generation: quantity, morphology, location, etc. The programme carried out in response to ITER needs for safety assessment comprises: (i) remotely controlled vacuum cleaning of the divertor; (ii) local sampling of loosely bound matter from plasma-facing components (PFC); (iii) collection of mobilized dust on various erosion-deposition probes located in the divertor and in the main chamber. Results of comprehensive analyses performed by a number of complementary techniques, e.g. a range of microscopy methods, electron and ion spectroscopy, liquid scintillography and thermal desorption, are summarized by following points: (a) Total amount of dust collected by vacuum cleaning after three campaigns is about 1–1.4 g per campaign (19.1–23.5 h plasma operation), i.e. over 100 times smaller than in JET operated with carbon walls (i.e. in JET-C). (b) Two major categories of Be dust are identified: flakes of co-deposits formed on PFC and droplets (2–10 μm in diameter). Small quantifies, below 1 g, of Be droplets and splashes are associated mainly with melting of beryllium limiters. (c) Tungsten dust occurs mainly as partly molten flakes originating from the W-coated tiles. |
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| 書誌情報 |
Fusion Engineering and Design 巻 136, 号 11, p. 579-586, 発行日 2018-11 |
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| 出版者 | ||||||
| 出版者 | Elsevier B.V. | |||||
| ISSN | ||||||
| 収録物識別子タイプ | ISSN | |||||
| 収録物識別子 | 0920-3796 | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1016/j.fusengdes.2018.03.027 | |||||
| 関連サイト | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | https://doi.org/10.1016/j.fusengdes.2018.03.027 | |||||
