Results 61 to 70 of about 150 (75)

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

Journal of Nuclear Materials, 2005
Abstract We report on impurity transport modeling using the DIVIMP code which is able to qualitatively reproduce the poloidal variation of non-recycling impurity penetration factor (PF NR ) found in C-Mod experiments: a lower PF NR is computed at the inboard (3.6%) and divertor target locations (0.7%) than at the outboard (11%).
I H Hutchinson, B Lipschultz, B Labombard   +2 more
exaly   +5 more sources

3D-DIVIMP(HC) code modeling of DIII-D DiMES porous plug injector experiments [PDF]

Journal of Nuclear Materials, 2011
Abstract 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 ...
P C Stangeby, A G Mclean
exaly   +3 more sources

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Impurity profiles at the JET divertor targets compared with the DIVIMP code

Journal of Nuclear Materials, 1992
In 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, P J Harbour, L D Horton
exaly   +2 more sources

DIVIMP modeling of the toroidally symmetrical injection of 13CH4 into the upper SOL of DIII-D [PDF]

Journal of Nuclear Materials, 2005
Abstract As part of a study of carbon–tritium co-deposition, we carried out an experiment on DIII-D involving a toroidally symmetric injection of 13CH4 at the top of a LSN discharge. A Monte Carlo code, DIVIMP-HC, which includes molecular breakup of hydrocarbons, was used to model the region near the puff.
J D Elder, P C Stangeby, S L Allen
exaly   +2 more sources

DIVIMP simulation of W transport in the SOL of JET H-mode plasmas

Physica Scripta, 2011
A Jarvinen, M Groth, K Krieger
exaly   +3 more sources

Code-code comparisons of DIVIMP's 'onion-skin model' and the EDGE2D fluid code

Journal of Nuclear Materials, 1997
Abstract 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
P.C. Stangeby, J.D. Elder, W. Fundamenski, A. Loarte, L.D. Horton, R. Simonini, A. Taroni, O.F. Matthews, R.D. Monk   +8 more
openaire   +2 more sources

Calculation of observable quantities using a divertor impurity interpretive code, DIVIMP

Journal of Nuclear Materials, 1992
Our 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
openaire   +1 more source

3D-DIVIMP-HC modeling analysis of methane injection into DIII-D using the DiMES porous plug injector

Journal of Nuclear Materials, 2009
Abstract 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
B D Bray, N H Brooks, J W Davis
exaly   +2 more sources

DIVIMP-B2-EIRENE modelling of 13C migration and deposition in ASDEX Upgrade L-mode plasmas

Journal of Nuclear Materials, 2010
André Xuereb, M Groth, K Krieger
exaly   +3 more sources

Simulation of tungsten impurity transport by DIVIMP under different divertor magnetic configurations on HL-3

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.
Yanjie Zhang, Chaofeng Sang, Jiaxian Li   +2 more
exaly   +2 more sources