Results 51 to 60 of about 246 (87)

Understanding the impact of divertor and main chamber ion fluxes on divertor closure in the DIII-D tokamak [PDF]

open access: yes
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
core  

Impurity screening studies in the Alcator C-Mod tokamak [PDF]

open access: yes, 1996
Bombard, B.   +11 more
core  

DIVIMP modeling of impurity flows and screening in Alcator C-Mod [PDF]

open access: yes, 2004
Bombard, B.   +4 more
core  

First attempt to quantify W7-X island divertor plasma by local experiment-model comparison [PDF]

open access: yes, 2021
Bozhenkov, S.   +26 more
core   +2 more sources

Local impurity puffing as a scrape-off layer diagnostic on the Alcator C-Mod tokamak [PDF]

open access: yes, 1996
Bombard, B.   +7 more
core  

Screening of recycling and non-recycling impurities in the Alcator C-Mod tokamak [PDF]

open access: yes, 1996
Bombard, B.   +11 more
core  

An Assessment of the Current Data Affecting Tritium Retention and its Use to Project Towards T Retention in ITER [PDF]

open access: yes, 2010
Davis, J.W.   +13 more
core  

A novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments [PDF]

open access: yes, 1998
Bombard, B.   +7 more
core  

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