Numerical modelling for divertor design of the WEST device with a focus on plasma–wall interactions-Reference-Cited by-同舟云学术

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Numerical modelling for divertor design of the WEST device with a focus on plasma–wall interactions

Published:2015-04-22 Issue:5 Volume:55 Page:053025
ISSN:0029-5515
Container-title:Nuclear Fusion
language:
Short-container-title:Nucl. Fusion

Author:

Bufferand H.,Ciraolo G.,Marandet Y.,Bucalossi J.,Ghendrih Ph.,Gunn J.,Mellet N.,Tamain P.,Leybros R.,Fedorczak N.,Schwander F.,Serre E.

Publisher

IOP Publishing

Subject

Condensed Matter Physics,Nuclear and High Energy Physics

Link

http://stacks.iop.org/0029-5515/55/i=5/a=053025/pdf

Reference29 articles.

1. The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment

2. Finalizing the ITER divertor design: The key role of SOLPS modeling

3. Near wall plasma simulation using penalization technique with the transport code SolEdge2D-Eirene

4. Density Regimes and Heat Flux Deposition in the WEST Shallow Divertor Configuration

5. The EIRENE and B2-EIRENE Codes

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