An analytical erosion model for divertor plates and limiter experiments in CHS

A. Sagara, N. Noda, R. Akiyama, H. Arimoto, H. Idei, H. Iguchi, O. Kaneko, T. Kohmoto, S. Kubo, N. Matsunami, K. Matsuoka, S. Morita, O. Motojima, K. Nishimura, S. Okamura, J. Rice, T. Shoji, C. Takahasi, Y. Takita, M. UedaH. Yamada, I. Yamada

研究成果: Contribution to journalArticle査読

6 被引用数 (Scopus)

抄録

A self-consistent analytical solution for net erosion of a divertor plate which is set perpendicular to magnetic field lines is presented. The primary flux profile of hydrogen and impurities except redepositing particles is externally given as well as the return ratio of sputtered atoms to the plate. In the direction along the divertor trace, all conditions are uniform. The ionization mean free path is assumed constant to simplify equations. The analytical solution is compared with net erosion experiments carried out in compact helical system (CHS) by exposing a graphite target to a neutral beam heated plasma column introduced perpendicularly to the target along the magnetic field lines through a 2 cm slit opened on a graphite limiter. After exposure to 98 discharges, the target surface is analyzed with Rutherford backscattering method. Deposition profiles of Ti and O impurities are very well explained with the analytical predictions.

本文言語英語
ページ(範囲)271-275
ページ数5
ジャーナルJournal of Nuclear Materials
196-198
C
DOI
出版ステータス出版済み - 12 1 1992
外部発表はい

All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 材料科学(全般)
  • 原子力エネルギーおよび原子力工学

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