Results 1 to 10 of about 44 (41)

Comparison of DIVIMP and EDGE2D-EIRENE tungsten transport predictions in JET edge plasmas

Nuclear Materials and Energy, 2020
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 ...
M Groth, A Jarvinen, D Harting
exaly   +3 more sources

Validation of EDGE2D-EIRENE and DIVIMP for W SOL transport in JET

Nuclear Materials and Energy, 2020
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 Kumpulainen, M Groth, G Corrigan
exaly   +3 more sources

Comparative modeling studies of carbon and tungsten impurity transport in the boundary plasma of EAST with a partially detached divertor condition

Nuclear Materials and Energy, 2022
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, Hui Wang, Rui Ding, Xiaoju Liu, Hang Si, Dahuan Zhu, Rong Yan, Ran Hai, Hai Xie, Junling Chen   +9 more
doaj   +1 more source

Implementation and validation of guiding centre approximation into ERO2.0

Contributions to Plasma Physics, Volume 62, Issue 5-6, June‐July 2022., 2022
Abstract The Monte‐Carlo code ERO2.0 uses full orbit resolution to follow impurity particles throughout the plasma volume to determine the local erosion and deposition fluxes on the plasma‐facing components of fusion devices in magnetic confinement fusion.
Sebastian Rode, Juri Romazanov, Dirk Reiser, Sebastijan Brezinsek, Christian Linsmeier, Alexander Pukhov   +5 more
wiley   +1 more source

SiC as a core-edge integrated wall solution in DIII-D

Nuclear Materials and Energy, 2023
Silicon carbide (SiC) is a promising material for use in a fusion reactor due to its low hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation [1,2].
S. Zamperini, T. Abrams, J. Nichols, E. Unterberg, A. Lasa, P. Stangeby, S. Bringuier, D. Rudakov, J.D. Elder   +8 more
doaj   +1 more source

OEDGE modeling of far-SOL tungsten impurity sources and screening in WEST

Nuclear Materials and Energy, 2022
The plasma background and impurity transport in the scrape-off layer (SOL) of the WEST tokamak are modeled for three discharges over a Psep power scan ranging between 1.5 and 2.35 MW. An extended modeling grid is used to investigate far-SOL sourcing from
J.B. Maeker, J.H. Nichols, D.C. Donovan, A. Grosjean, J. Gunn, N. Fedorczak, C. Guillemaut, C.C. Klepper, E.A. Unterberg, D.C. Easley, WEST Team   +10 more
doaj   +1 more source

The transport of tungsten impurities induced by the intrinsic carbon during upper-single null discharge on EAST tokamak

Nuclear Materials and Energy, 2020
The transport as well as accumulation of tungsten (W) impurity is one of the critical issues for the W divertor operation. The EAST tokamak with W and graphite divertor targets, provides a good platform for the investigation of W impurity behaviors.
Qingrui Zhou, Chaofeng Sang, Guoliang Xu, Rui Ding, Xuele Zhao, Yilin Wang, Dezhen Wang   +6 more
doaj   +1 more source

Modeling the effect of nitrogen recycling on the erosion and leakage of tungsten impurities from the SAS-VW divertor in DIII-D during nitrogen gas injection

Nuclear Materials and Energy, 2022
The new SAS-VW divertor in DIII-D has tungsten-coated components to enable the study of tungsten erosion and leakage from a closed, slot-like divertor. A proposed method of actively managing the tungsten impurities is to inject low-Z impurities, such as ...
Matthew S. Parsons, Gregory Sinclair, Tyler Abrams   +2 more
doaj   +1 more source

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

Nuclear Fusion, 2023
Tungsten (W) is used as the plasma-facing material in the divertor region of future fusion reactors, such as ITER; however, its concentration in the core plasma must be maintained at an extremely low level.
Jin Guo, Yuchen Xu, Shifeng Mao, Minyou Ye   +3 more
doaj   +1 more source

Tungsten core accumulation study in EAST plasma with lower tungsten divertor by kinetic impurity transport model

Nuclear Materials and Energy, 2022
Tungsten (W) impurity transport and the corresponding core W accumulation is a critical issue in tokamak with W as plasma facing material. In this work, a kinetic W impurity transport code based on the guiding center approximation is applied for the ...
Yihan Wu, Qingrui Zhou, Chaofeng Sang, Yanjie Zhang, Yilin Wang, Dezhen Wang   +5 more
doaj   +1 more source