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Numerical analysis of tungsten erosion and deposition processes under a DEMO divertor plasma and geometry
https://repo.qst.go.jp/records/48961
https://repo.qst.go.jp/records/48961289e8c47-3049-45c9-b967-c2a2407b718b
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-01-11 | |||||
| タイトル | ||||||
| タイトル | Numerical analysis of tungsten erosion and deposition processes under a DEMO divertor plasma and geometry | |||||
| 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 |
Homma, Yuki
× Homma, Yuki× Hoshino, Kazuo× Yamoyo, Shohei× Asakura, Nobuyuki× Tokunaga, Shinsuke× Hatayama, Akiyoshi× Sakamoto, Yoshiteru× Hiwatari, Ryoji× Tobita, Kenji× Special Design Team for Fusion DEMO, Joint× Homma, Yuuki× Hoshino, Kazuo× Asakura, Nobuyuki× Tokunaga, Shinsuke× Sakamoto, Yoshiteru× Hiwatari, Ryoji× Tobita, Kenji |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Erosion reduction of tungsten (W) divertor target is one of the most important research subjects for the DEMO fusion reactor design, because the divertor target has to sustain large fluence of incident particles, composed mainly of fuel ions and seeded impurities, during year-long operation period. Rate of net erosion and deposition on outer divertor target has been studied by using the integrated SOL/divertor plasma code SONIC and the kinetic full-orbit impurity transport code IMPGYRO. Two background plasmas have been used: one is lower density ni and higher temperature case and the other is higher ni and lower temperature case. Net erosion has been seen in the lower ni case. But in the higher ni case, the net erosion has been almost suppressed due to increased return rate and reduced self-sputtering yield. Following two factors play important roles for net erosion formation: (i) relation between the 1st ionization length of sputtered W atom and the Larmor gyro radius of W+ ion, (ii) balance between the friction force and the thermal force exerted on W ions. DEMO divertor design should take into account these factors to prevent target erosion. | |||||
| 書誌情報 |
Nuclear Materials and Energy 巻 12, p. 323-328, 発行日 2017-05 |
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| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1016/j.nme.2017.05.003 | |||||
