Micro-trench measurements of the net deposition of carbon impurity ions in the DIII-D divertor and the resulting suppression of surface erosion-Reference-Cited by-同舟云学术

Micro-trench measurements of the net deposition of carbon impurity ions in the DIII-D divertor and the resulting suppression of surface erosion

Published:2021-10-11 Issue:12 Volume:96 Page:124039
ISSN:0031-8949
Container-title:Physica Scripta
language:
Short-container-title:Phys. Scr.

Author:

Abe S^ORCID,Skinner C H,Bykov I,Guterl J^ORCID,Lasa A^ORCID,Yeh Y W,Coburn J^ORCID,Rudakov D L^ORCID,Lasnier C J,Wang H Q^ORCID,McLean A G,Abrams T^ORCID,Koel B E

Funder

Office of Science

Publisher

IOP Publishing

Subject

Condensed Matter Physics,Mathematical Physics,Atomic and Molecular Physics, and Optics

Link

https://iopscience.iop.org/article/10.1088/1402-4896/ac2af4/pdf

Reference29 articles.

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2. ERO modeling and analysis of tungsten erosion and migration from a toroidally symmetric source in the DIII-D divertor;Guterl;Nucl. Fusion,2020

3. Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade;Dux;J. Nucl. Mater.,2009

4. Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET;van Rooij;J. Nucl. Mater,2013

5. ELM-resolved divertor erosion in the JET ITER-Like Wall;Den Harder;Nucl. Fusion,2016

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1. A tutorial on the micro-trench technique for incident ion angle, material erosion, and impurity deposition measurements at plasma-facing surfaces;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2024-11

2. Assessment of carbon net erosion/deposition at the divertor of W7-X;Nuclear Materials and Energy;2023-03

3. Carbon erosion/deposition on the divertor of W7-X during the operational period OP 1.2b;Nuclear Fusion;2022-10-31

4. Computational investigation of incident ion angles and material erosion at rough graphite and silicon carbide divertor surfaces;Physics of Plasmas;2022-10

5. Determination of the characteristic magnetic pre-sheath length at divertor surfaces using micro-engineered targets on DiMES at DIII-D;Nuclear Fusion;2021-11-24