Pedestal fueling through interpretive analysis of measured main chamber and divertor target flux in DIII-D
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference12 articles.
1. Assessment of the poloidal distribution of core plasma fueling and impurity sources in DIII-D
2. Simulation of main-chamber recycling in DIII-D with the UEDGE code
3. Particle flux and radial profiles in the SOL of DIII-D during ELMing H-mode
4. The magnitude of plasma flux to the main-wall in the DIII-D tokamak
5. Comparison of particle transport in the scrape-off layer plasmas of Alcator C-Mod and DIII-D
Cited by 8 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. First Evidence of Local E×B Drift in the Divertor Influencing the Structure and Stability of Confined Plasma near the Edge of Fusion Devices;Physical Review Letters;2020-05-13
2. SOLPS analysis of changes in the main SOL of DIII-D associated with divertor detachment vs attachment and closure vs openness;Nuclear Fusion;2020-04-06
3. Separating divertor closure effects on divertor detachment and pedestal shape in DIII-D;Physics of Plasmas;2020-03
4. Recombination of H atoms on the dust in fusion plasmas;Physics of Plasmas;2015-07
5. Detailed OEDGE modeling of core-pedestal fueling in DIII-D;Journal of Nuclear Materials;2013-07
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