Results 11 to 20 of about 18,296 (224)

Impurity transport and halo current effects on tungsten divertor system

open access: yesJournal of Radiation Research and Applied Sciences, 2020
This paper presents the development of theoretical model for the purpose to calculate and analyze halo and eddy current effects in the tungsten divertor of Tokamak (Fusion) reactor.
Shahab Ud-Din Khan   +5 more
openaire   +3 more sources

Comparison of kinetic and fluid models for tungsten impurity transport using IMPGYRO and SOLPS [PDF]

open access: yesJournal of Nuclear Materials, 2013
Abstract A benchmark calculation of tungsten impurity transport comparing kinetic modeling with IMPGYRO and multi-fluid modeling with SOLPS has been performed. The primary source of tungsten has been set at the outer mid-plane in the calculations. In both cases, impurity densities are relatively large in the SOL region near the top of the machine ...
Toma, M.   +7 more
openaire   +5 more sources

Reproduction of collector probe deposition profiles using the far-SOL impurity transport code 3DLIM

open access: yesNuclear Materials and Energy, 2020
First results are reported from the 3D Monte Carlo far-SOL impurity transport code 3DLIM. Tungsten deposition profiles measured on a Collector Probe (CP) located in the far-SOL near the outer midplane, OMP, during W tracer experiments in DIII-D are ...
S.A. Zamperini   +7 more
doaj   +3 more sources

Modelling of tungsten erosion and deposition in the divertor of JET-ILW in comparison to experimental findings

open access: yesNuclear Materials and Energy, 2019
The erosion, transport and deposition of tungsten in the outer divertor of JET-ILW has been studied for an H-Mode discharge with low frequency ELMs.
A. Kirschner   +11 more
doaj   +3 more sources

DIVIMP modeling of tungsten impurity transport in ITER [PDF]

open access: yesJournal of Nuclear Materials, 2007
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 ...
Schmid, K.   +3 more
openaire   +3 more sources

Tungsten erosion and divertor leakage from the DIII-D SAS-VW tungsten-coated divertor in experiments with neon gas seeding

open access: yesNuclear Materials and Energy, 2023
Collector probes have been used to examine tungsten divertor leakage in a variety of scenarios with low-Z impurity seeding during operation with the new tungsten-coated SAS-VW divertor in DIII-D.
Matthew S. Parsons   +15 more
doaj   +1 more source

Refining light impurity content estimates at the lower divertor based on experimental data in WEST

open access: yesNuclear Materials and Energy, 2023
WEST is an actively cooled, long-pulse tokamak with nearly all plasma-facing components (PFC) made of tungsten (W). One of the aims of WEST is to study plasma operation with W PFCs in preparation for long-pulse operation on W divertor devices like ITER ...
A. Grosjean   +7 more
doaj   +1 more source

Overview of ASDEX Upgrade results [PDF]

open access: yes, 2017
The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and the preparation of ITER operation, as well as addressing physics issues for a future DEMO design.
ASDEX Upgrade Team   +2 more
core   +4 more sources

Preliminary Result of Neoclassical Impurity Transport Affected by ICRH with a 4-D Fokker-Planck Code [PDF]

open access: yesEPJ Web of Conferences
To understand the role of ion cyclotron resonance heating (ICRH) in mitigating tungsten accumulation, we evaluate the impact of ICRH-induced poloidal asymmetries on neoclassical impurity transport using a newly developed 4-D Fokker–Planck code (FP4D ...
Jeong Yunho   +4 more
doaj   +1 more source

Overview of the JET results in support to ITER [PDF]

open access: yes, 2017
The 2014–2016 JET results are reviewed in the light of their significance for optimising the ITER research plan for the active and non-active operation. More than 60 h of plasma operation with ITER first wall materials successfully took place since its
Abduallev, S.   +7 more
core   +1 more source

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