Fuelling and disruption mitigation in ITER

S. Maruyama, Y. Yang, M. Sugihara, R. A. Pitts, L. Baylor, S. Combs, S. Meitner, B. Li, W. Li

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

11 Scopus citations

Abstract

The ITER tokamak is to be fueled mainly by pellet injection and gas puffing to control discharge parameters. The ITER pellet injection system (PIS) will be the main plasma density control tool for fuelling ITER and also provides ELM pacing functionality. The gas injection system (GIS) provides gas fuelling for plasma and wall conditioning operation, and H2 and D2 gases to NB injectors. The fuelling system also serves the critical function of disruption mitigation, including the suppression of runaway electrons resulting from the mitigation. This paper presents an overview of the ITER fuelling system design and development, the requirements that the disruption mitigation system (DMS) must satisfy and the development strategy to ensure that a reliable DMS is in place for the start of ITER operations.

Original languageEnglish
Title of host publication2009 23rd IEEE/NPSS Symposium on Fusion Engineering, SOFE 2009
DOIs
StatePublished - 2009
Event2009 23rd IEEE/NPSS Symposium on Fusion Engineering, SOFE 2009 - San Diego, CA, United States
Duration: Jun 1 2009Jun 5 2009

Publication series

NameProceedings - Symposium on Fusion Engineering

Conference

Conference2009 23rd IEEE/NPSS Symposium on Fusion Engineering, SOFE 2009
Country/TerritoryUnited States
CitySan Diego, CA
Period06/1/0906/5/09

Keywords

  • Component; ITER
  • Disruption mitigation
  • ELM pacing
  • Fuelling
  • Gas injection
  • Pellet injection
  • Plasma control

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