Numerical modelling of the impact of leakage under divertor baffle in WEST-Reference-Cited by-同舟云学术

Numerical modelling of the impact of leakage under divertor baffle in WEST

Published:2022-10 Issue: Volume:33 Page:101302
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Yang H.^ORCID,Ciraolo G.,Bucalossi J.,Bufferand H.^ORCID,Fedorczak N.^ORCID,Tamain P.^ORCID,Falchetto G.,Rivals N.^ORCID,Gunn J.P.,Marandet Y.,Pégourié B.,Vartanian S.

Funder

EUROfusion Consortium Research Institutions

European Commission

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

Reference28 articles.

1. Status and physics basis of the ITER divertor;Pitts;Phys. Scr.,2009

2. The Plasma Boundary of Magnetic Fusion Devices, Vol. 224;Stangeby,2000

3. Plasma detachment in divertor tokamaks;Leonard;Plasma Phys. Control. Fusion,2018

4. Numerical investigation of optimal divertor gas baffle closure on TCV;Galassi;Plasma Phys. Control. Fusion,2020

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

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1. Numerical study of a general criterion for divertor detachment control;Nuclear Fusion;2024-09-03

2. Global particle buildup simulations with gas puff scan: application to WEST discharge;Frontiers in Physics;2024-08-14

3. Self‐organization of plasma edge turbulence in interaction with recycling neutrals;Contributions to Plasma Physics;2024-02-26

4. Calorimetry measurement for energy balance and energy distribution in WEST for L-mode plasmas;Nuclear Fusion;2024-02-09

5. Numerical study of divertor detachment in TCV H-mode scenarios;Plasma Physics and Controlled Fusion;2023-11-02