Erosion estimates for the divertor and main wall components from STEP
A Kirschner, SS Henderson, S Brezinsek… - Nuclear …, 2023 - iopscience.iop.org
The tungsten erosion within Spherical Tokamak for Energy Production (STEP) assuming
tungsten main wall and tungsten divertor has been estimated with ERO at the inner and …
tungsten main wall and tungsten divertor has been estimated with ERO at the inner and …
[HTML][HTML] Simulation study of the influence of the outer target geometry on tungsten contamination: Horizontal vs. vertical target
H Ding, J Guo, S Mao, X Ruan, Y Xu, M Ye - Nuclear Materials and Energy, 2024 - Elsevier
The core tungsten (W) concentration must be limited to an extremely low level for future
fusion reactors. It was found that the effects of E× B drift can lead to a dramatic increase in …
fusion reactors. It was found that the effects of E× B drift can lead to a dramatic increase in …
[HTML][HTML] Simulation studies of tungsten impurity behaviors in helium plasma in comparison with deuterium plasma via SOLPS-ITER
X Liu, S Gao, Q Shi, T Ming, G Li, X Gao - Physics of Plasmas, 2024 - pubs.aip.org
The sputtering and transport of tungsten (W) impurities in helium (He) and deuterium (D)
plasma discharges are compared using the SOLPS-ITER code. To reduce the computational …
plasma discharges are compared using the SOLPS-ITER code. To reduce the computational …
Modeling of tungsten divertor target erosion induced by impurity during edge‐localized modes by using a kinetic model
C Wang, C Sang, J Liu, C Zhang… - Contributions to Plasma …, 2024 - Wiley Online Library
The burst of edge‐localized modes (ELMs) leads to an increase in the energy and particle
fluxes to the divertor target. Tungsten (W) is chosen as the primary candidate material for …
fluxes to the divertor target. Tungsten (W) is chosen as the primary candidate material for …
Simulation of tungsten impurity transport by DIVIMP under different divertor magnetic configurations on HL-3
Z Qingrui, Y Zhang, S Chaofeng… - Plasma Science and …, 2024 - iopscience.iop.org
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) …
edge region, is a severe issue in fusion reactors. Compared to standard divertors (SDs) …
[PDF][PDF] Effects of drift on the tungsten impurity accumulation in the core of tokamak during insert gas seeding
C Sang, Y Wu, Y Wang, Q Zhou, Y Luo, D Wang - aappsdpp.org
Tungsten (W) is taken as the main candidate for the plasma-facing materials (PFMs) of the
future fusion devices such as ITER, DEMO and CFETR. However, as high-Z impurity, W is …
future fusion devices such as ITER, DEMO and CFETR. However, as high-Z impurity, W is …