Fuelling and disruption mitigation in ITER

Author

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

Author_Institution

ITER Organ., St. Paul-lez-Durance, France

fYear

2009

fDate

1-5 June 2009

Firstpage

1

Lastpage

4

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.

Keywords

Tokamak devices; discharges (electric); fusion reactor design; fusion reactor fuel; fusion reactor operation; plasma density; D₂ gases; ELM pacing functionality; H₂ gases; ITER tokamak operations; discharge parameters; disruption mitigation; disruption mitigation system; fuelling; fusion reactor design; gas puffing; pellet injection system; plasma density control tool; runaway electrons; wall conditioning operation; Control systems; Electrons; Gases; Geographic Information Systems; Niobium; Plasma density; Tokamaks; Disruption Mitigation; ELM Pacing; Fuelling; Gas Injection; ITER; Pellet Injection; Plasma control; component;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on

Conference_Location

San Diego, CA

Print_ISBN

978-1-4244-2635-5

Electronic_ISBN

978-1-4244-2636-2

Type

conf

DOI

10.1109/FUSION.2009.5226494

Filename

5226494