Understanding the impact of divertor and main chamber ion fluxes on divertor closure in the DIII-D tokamak [PDF]
The diverted tokamak redirects extreme heat and particles to targets, a plasma-facing component designed for such loads. Here, the local fluxes produce strong particle recycling and sputtering.
Davda, Kirtan M
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Tungsten as first wall material in fusion devices. Invited [PDF]
Kaufmann, M., Neu, R.
core +2 more sources
DIVIMP modeling of impurity flows and screening in Alcator C-Mod [PDF]
Bombard, B. +4 more
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First attempt to quantify W7-X island divertor plasma by local experiment-model comparison [PDF]
Bozhenkov, S. +26 more
core +2 more sources
Local impurity puffing as a scrape-off layer diagnostic on the Alcator C-Mod tokamak [PDF]
Bombard, B. +7 more
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Screening of recycling and non-recycling impurities in the Alcator C-Mod tokamak [PDF]
Bombard, B. +11 more
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Nitrogen implantation in tungsten and migration in the fusion experiment ASDEX Upgrade
Meisl, G.
core +1 more source
An Assessment of the Current Data Affecting Tritium Retention and its Use to Project Towards T Retention in ITER [PDF]
Davis, J.W. +13 more
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A novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments [PDF]
Bombard, B. +7 more
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