Simulation of hydrocarbon redeposition in the gaps between divertor tiles
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference11 articles.
1. Tritium Retention in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and TFTR
2. Carbon deposition in the gaps between tiles: Data from the Tokamak Fusion Test Reactor and laboratory simulation studies
3. R.K. Janev, D. Reiter, Rep. Forschungszentrum Jülich, Jül-3966, 2002.
4. Simulation of redeposition patterns of hydrocarbons released from carbon target in divertors
5. The Plasma Boundary of Magnetic Fusion Devices;Stangeby,2000
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1. Hydrogen Isotopes Retention in Gaps at the JT-60U First Wall Tiles;Fusion Science and Technology;2013-05
2. Tritium Retention in First Wall Tile Gaps of JT-60U;Fusion Science and Technology;2012-08
3. Investigations of the origins of deposited carbon species in gaps between divertor tiles using a kinetic code system;Fusion Engineering and Design;2012-08
4. A Kinetic Code System to Study Impurity Deposition and Fuel Retention in Gaps Between Divertor Tiles;Contributions to Plasma Physics;2012-05
5. Deuterium concentration of co-deposited carbon layer produced at gap of wall tiles;Journal of Nuclear Materials;2011-10
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