Toroidal and poloidal asymmetry in carbon deposition on gaps of plasma facing tiles
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Deuterium inventory in Tore Supra: reconciling particle balance and post-mortem analysis
2. Tritium Retention in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and TFTR
3. DiMES studies of temperature dependence of carbon erosion and re-deposition in the lower divertor of DIII-D under detachment
4. Fuel Inventory and Co-Deposition in Grooves and Gaps of Divertor and Limiter Structures
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1. Erosion and Deposition, and Their Influences on Plasma Behavior (Material Transport in Tokamak);Plasma-Material Interactions in a Controlled Fusion Reactor;2021
2. Effects of the divertor tile geometries and magnetic field angles on the heat fluxes to the surface;Fusion Engineering and Design;2017-03
3. Divertor tungsten tiles erosion in the region of the castellated gaps;Fusion Engineering and Design;2016-11
4. Hydrogen Isotopes Retention in Gaps at the JT-60U First Wall Tiles;Fusion Science and Technology;2013-05
5. Modelling of local carbon deposition on a rough test limiter exposed to the edge plasma of TEXTOR;Plasma Physics and Controlled Fusion;2013-04-10
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