Results 71 to 80 of about 246 (87)
Some of the next articles are maybe not open access.
Assessment of the DIVIMP ‘onion-skin’ model in the JET Mark I divertor
Journal of Nuclear Materials, 1997Abstract The DIVIMP-NIMBUS [1] ‘Onion-Skin’ model has been used to predict upstream plasma parameters using as input measurements by Langmuir probes in the divertor target tiles. Measurements of density and temperature (both Ti and Te) across the SOL close to the stagnation point at the top of the torus have been made using a reciprocating probe ...
S.K. Erents +8 more
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Impurity profiles at the JET divertor targets compared with the DIVIMP code
Journal of Nuclear Materials, 1992In this paper we describe the simulation of edge diagnostics in JET using the DIVIMP (divertor impurity) Monte Carlo code. We concentrate on two ohmic pulses and show how the results are influenced by a variety of modeling assumptions. Our results show that a wall source must be included to explain the diagnostic signals. The wall source is shown to be
G.F. Matthews +17 more
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Calculation of observable quantities using a divertor impurity interpretive code, DIVIMP
Journal of Nuclear Materials, 1992Our picture of divertor edge plasma behaviour is largely theoretical with little experimental confirmation. Questions exist with regard to impurity production mechanisms, sputtering yields, plasma ion temperatures, parallel temperature gradients, the existence of plasma flow reversal, cross-field diffusion coefficients, etc.
P.C. Stangeby, J.D. Elder
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3D-DIVIMP(HC) code modeling of DIII-D DiMES porous plug injector experiments
Journal of Nuclear Materials, 2011Abstract A Porous Plug Injector (PPI) system for the Divertor Material Evaluation System (DiMES) on DIII-D has been employed for in situ study of chemical erosion in the tokamak divertor environment. The 3D-DIVIMP(HC) code has been applied to the interpretation of the CI, CII and other spectroscopic measurements made at the PPI location, for (a) the ...
Y. Mu +3 more
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Code-code comparisons of DIVIMP's 'onion-skin model' and the EDGE2D fluid code
Journal of Nuclear Materials, 1997Abstract In onion-skin modelling, O-SM, of the edge plasma, the cross-field power and particle flows are treated very simply e.g. as spatially uniform. The validity of O-S modelling requires demonstration that such approximations can still result in reasonable solutions for the edge plasma. This is demonstrated here by comparison of O-SM with full 2D
W Fundamenski
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3D-DIVIMP-HC modeling analysis of methane injection into DIII-D using the DiMES porous plug injector
Journal of Nuclear Materials, 2009Abstract A self-contained gas injection system for the Di vertor M aterial E valuation S ystem (DiMES) on DIII-D, the porous plug injector (PPI), has been employed for in situ study of chemical erosion in the tokamak divertor environment by injection of CH 4 [A.G. McLean et al., these Proceedings]. A new interpretive code, 3D-DIVIMP-HC, has been
Y. Mu +13 more
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Journal of Nuclear Materials, 2003
Tungsten erosion at the central column and tungsten transport in the scrape-off layer of ASDEX Upgrade have been modeled with the 2D Monte-Carlo impurity transport code DIVIMP. The main objectives were the reproduction of the erosion and migration patterns that are observed experimentally.
Geier, A. +5 more
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Tungsten erosion at the central column and tungsten transport in the scrape-off layer of ASDEX Upgrade have been modeled with the 2D Monte-Carlo impurity transport code DIVIMP. The main objectives were the reproduction of the erosion and migration patterns that are observed experimentally.
Geier, A. +5 more
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Journal of Nuclear Materials, 2007
Abstract 13CH4 , 12CD4 or 12CH4 gases were puffed into the crown (top) of lower single-null divertor plasmas in DIII-D using toroidally symmetric injection, constituting a particularly simple experiment to interpret. The resulting CI (9094.83 A) wavelength profiles were measured with a high resolution spectrometer.
P.C. Stangeby +5 more
exaly +2 more sources
Abstract 13CH4 , 12CD4 or 12CH4 gases were puffed into the crown (top) of lower single-null divertor plasmas in DIII-D using toroidally symmetric injection, constituting a particularly simple experiment to interpret. The resulting CI (9094.83 A) wavelength profiles were measured with a high resolution spectrometer.
P.C. Stangeby +5 more
exaly +2 more sources
DIVIMP-B2-EIRENE modelling of 13C migration and deposition in ASDEX Upgrade L-mode plasmas
Journal of Nuclear Materials, 2010Xuereb, A. +8 more
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Plasma Science and Technology
Abstract Tungsten (W) accumulation in the core, depending on W generation and transport in the edge region, is a severe issue in fusion reactors. Compared to standard divertors (SDs), snowflake divertors (SFDs) can effectively suppress the heat flux, while the impact of magnetic configurations on W core accumulation remains unclear.
Qingrui 庆瑞 ZHOU 周 +7 more
openaire +1 more source
Abstract Tungsten (W) accumulation in the core, depending on W generation and transport in the edge region, is a severe issue in fusion reactors. Compared to standard divertors (SDs), snowflake divertors (SFDs) can effectively suppress the heat flux, while the impact of magnetic configurations on W core accumulation remains unclear.
Qingrui 庆瑞 ZHOU 周 +7 more
openaire +1 more source

