Suppression of net erosion in the DIII-D divertor with detached plasmas
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference18 articles.
1. Divertor erosion in DIII-D
2. In-vessel tritium retention and removal in ITER
3. Radiative divertor experiments in DIII-D with D2injection
4. Scaling and profiles of heat flux during partial detachment in DIII-D
5. Divertor materials evaluation system (DiMES)
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1. Assessing material migration through 13C injection experiments;Journal of Nuclear Materials;2011-08
2. An EDDY/Particle-in-Cell Simulation of Erosion of Plasma Facing Walls Bombarded by a Collisional Plasma;Japanese Journal of Applied Physics;2011-02-21
3. An EDDY/Particle-in-Cell Simulation of Erosion of Plasma Facing Walls Bombarded by a Collisional Plasma;Japanese Journal of Applied Physics;2011-02-01
4. The maintenance of good wall conditions and high performance operation on DIII-D over extended periods without boronization;Plasma Physics and Controlled Fusion;2009-03-19
5. Transport and deposition of 13C from methane injection into partially detached H-mode plasmas in DIII-D;Journal of Nuclear Materials;2007-06
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