Validation of EDGE2D-EIRENE and DIVIMP for W SOL transport in JET [PDF]
Tungsten sputtering rates and density profiles predicted using the edge plasma codes EDGE2D-EIRENE and DIVIMP are found to agree within a factor of 4 with measurements of neutral and singly-ionized W spectral line emission in the JET low-field side (LFS)
H.A. Kumpulainen +8 more
doaj +21 more sources
Detachment evolution on the TCV tokamak [PDF]
Divertor detachment in the TCV tokamak has been investigated through experiments and modelling. Density ramp experiments were carried out in ohmic heated L-mode pulses with the ion ∇B drift directed away from the primary X-point, similar to previous ...
J.R. Harrison +13 more
doaj +6 more sources
DIVIMP modelling of tungsten impurity transport in ITER [PDF]
This paper presents a modeling study of the W erosion and plasma accumulation in ITER for different levels of first wall W coverage and plasma configurations using the Monte Carlo impurity transport code DIVIMP. Based on the ion fluxes from the background plasma solutions from B2/EIRENE the W erosion is calculated by taking into account both D and ...
Krieger, K. +3 more
core +4 more sources
Comparison of DIVIMP and EDGE2D-EIRENE tungsten transport predictions in JET edge plasmas
The average tungsten concentrations in the pedestal region (cW) predicted by the Monte Carlo code DIVIMP and the coupled multi-fluid plasma/kinetic neutral code EDGE2D-EIRENE are found to agree within a factor of 2 for a range of JET-ILW L-mode and H ...
H.A. Kumpulainen +5 more
doaj +3 more sources
DIVIMP simulations of 13C puffing experiments in ASDEX Upgrade L-mode plasma [PDF]
Carbon migration has been investigated both experimentally and numerically by injecting isotopically marked methane (13CH4) at trace levels into a series of identical low-density, low-confinement mode discharges at the last day of the 2007 ASDEX Upgrade experimental campaign.
Makkonen, T. +9 more
exaly +6 more sources
DIVIMP modeling of impurity flows and screening in Alcator C-Mod [PDF]
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%).
T. Chung +4 more
exaly +2 more sources
DIVIMP modeling of the toroidally symmetrical injection of 13CH4 into the upper SOL of DIII-D [PDF]
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.
Dmitry Rudakov
exaly +2 more sources
Impurity transport modelling in the scrape off layer of the MAST tokamak using DIVIMP-OSM-EIRENE and carbon injection [PDF]
Non-hydrogenic impurities play a significant role in the performance of magnetically confined fusion devices, causing increased radiation and dilution of the Deuterium-Tritium fuel isotopes.
Leggate, Huw J.
core +2 more sources
Diverted Tokamak Carbon Screening: Scaling with Machine Size and Consequences to Core Contamination [PDF]
core +2 more sources
The source and leakage of both C and W are comparatively studied for a partially detached divertor operation condition on EAST. Based on the EAST experiments, sequential SOLPS-DIVIMP simulations are carried out to study the transport of intrinsic ...
Guoliang Xu +9 more
doaj +1 more source

