A control method of divertor plasma start-up assisted by tritium-ratio control for Demo-CREST

R. Hiwatari, K. Okano, M. Ishida, K. Maeki, A. Hatayama, Y. Ogawa, M. Nakamura

研究成果: Article査読

2 被引用数 (Scopus)

抄録

In this paper, core plasma operation flexibility by the tritium-ratio(T-ratio) control is proposed in order to control the fusion power keeping a high plasma density for the divetor heat-handling during the commissioning phase. The operational space of the core plasma for the Demo-CREST concept is expanded to the high density region by reducing T-ratio. Especially, the expansion of operation space for the low beta operation is large. For such operation expansion, the critical parameter is the confinement improvement factor HH, and a high HH similar to that of the ITER steady state (ITER-SS) operation is required for Demo-CREST. The resultant condition of the SOL density and the impurity radiation power required for the divertor heat load less than 10 MW/m2 is analyzed, and those operation conditions for the initial operation point of the fusion power 0 MW during the commissioning phase are found to be similar to those of the ITER-SS operation.

本文言語English
ページ(範囲)1099-1102
ページ数4
ジャーナルFusion Engineering and Design
86
6-8
DOI
出版ステータスPublished - 2011 10

ASJC Scopus subject areas

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学

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