Modelling of tungsten contamination and screening in WEST plasma discharges-Reference-Cited by-同舟云学术

Modelling of tungsten contamination and screening in WEST plasma discharges

Published:2021-09-13 Issue:10 Volume:61 Page:106019
ISSN:0029-5515
Container-title:Nuclear Fusion
language:
Short-container-title:Nucl. Fusion

Author:

Di Genova S.^ORCID,Gallo A.^ORCID,Fedorczak N.,Yang H.,Ciraolo G.,Romazanov J.^ORCID,Marandet Y.,Bufferand H.,Guillemaut C.,Gunn J.P.,Gil C.,Serre E.^ORCID,Brezinsek S.^ORCID,the WEST Team

Funder

H2020 Euratom

Publisher

IOP Publishing

Subject

Condensed Matter Physics,Nuclear and High Energy Physics

Link

https://iopscience.iop.org/article/10.1088/1741-4326/ac2026/pdf

Reference41 articles.

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2. The WEST project: testing ITER divertor high heat flux component technology in a steady state tokamak environment;Bucalossi;Fusion Eng. Des.,2014

3. Visible spectroscopy diagnostics for tungsten source assessment in the WEST tokamak: first measurements;Meyer;Rev. Sci. Instrum.,2018

4. Tungsten divertor sources in WEST related to impurity inventory and local plasma conditions;van Rooij;Phys. Scr.,2020

5. Numerical modelling for divertor design of the WEST device with a focus on plasma–wall interactions;Bufferand;Nucl. Fusion,2015

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