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

Research output: Contribution to journalArticle

2 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)1099-1102
Number of pages4
JournalFusion Engineering and Design
Volume86
Issue number6-8
DOIs
Publication statusPublished - 2011 Oct 1

Keywords

  • Commissioning operation
  • Demo-CREST
  • Demonstration reactor
  • Divertor plasma
  • Tritium ratio control

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

Fingerprint Dive into the research topics of 'A control method of divertor plasma start-up assisted by tritium-ratio control for Demo-CREST'. Together they form a unique fingerprint.

  • Cite this

    Hiwatari, R., Okano, K., Ishida, M., Maeki, K., Hatayama, A., Ogawa, Y., & Nakamura, M. (2011). A control method of divertor plasma start-up assisted by tritium-ratio control for Demo-CREST. Fusion Engineering and Design, 86(6-8), 1099-1102. https://doi.org/10.1016/j.fusengdes.2011.03.041