Porous plug gas injection systems for studies of hydrocarbon dissociation and transport in the DIII-D tokamak
Author:
Publisher
AIP Publishing
Subject
Instrumentation
Link
http://aip.scitation.org/doi/pdf/10.1063/1.3100180
Reference19 articles.
1. Oxygen removal of codeposited a-C:D layers from tokamak tiles
2. Chemical erosion behaviour of carbon materials in fusion devices
3. Chemical erosion of DIII-D lower divertor tiles
4. Measurement of CH4/CD4 fluxes and of chemical carbon erosion from CH/CD band emission
5. Chemical Erosion Measurements in Tokamaks by Spectroscopy
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1. 13C surface characterization of midplane and crown collector probes on DIII-D;Nuclear Materials and Energy;2023-03
2. Material testing facilities and programs for plasma-facing component testing;Nuclear Fusion;2017-06-09
3. Divertor impurity injection using high voltage arcs for impurity transport studies on the Mega Amp Spherical Tokamak;Review of Scientific Instruments;2014-12
4. The influence of three-dimensional stochastic magnetic boundaries on plasma edge transport and the resulting plasma wall interaction;Journal of Nuclear Materials;2011-08
5. Quantification of chemical erosion in the DIII-D divertor and implications for ITER;Journal of Nuclear Materials;2011-08
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