Abstract
Though helium plasmas are one option for the low activation phase of ITER, little effort has thus far been devoted to studying them in a large, diverted tokamak. A recent campaign on JET has therefore sought to address some of the important questions related to helium operation (He concentrations near 90%) in single null configuruations, particularly with regard to edge and divertor physics. This contribution compiles a selection of results from these experiments, in which, in each case, discharges have been chosen to match as closely as possible previous, well characterised D plasmas in both L and ELMing H-modes. These matched pulses are used to draw conclusions regarding the principle source and location of carbon production in D plasmas, to compare and contrast the mechanisms of the density limit and the detachment process in D and He, to investigate the nature of cross-field power transport in the SOL and to gain insight into the process by which ELM energy is transported to the divertor targets.
Original language | English |
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Pages (from-to) | 777-786 |
Number of pages | 10 |
Journal | Journal of Nuclear Materials |
Volume | 313-316 |
Issue number | SUPPL. |
DOIs | |
State | Published - Mar 2003 |
Externally published | Yes |
Event | Plasma - Surface Interactions in Controlled Fusion Devices - Gifu, Japan Duration: May 26 2002 → May 31 2002 |
Funding
This work was performed under the European Fusion Development Agreement and was supported in part by the Swiss National Science Foundation, EURATOM and the UK Department of Trade and Industry.
Funders | Funder number |
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H2020 Euratom | |
Schweizerischer Nationalfonds zur Förderung der Wissenschaftlichen Forschung | |
Department of Trade and Industry |
Keywords
- Carbon source
- Density limit
- Detachment
- Divertor
- Helium
- Tokamak