Results 191 to 200 of about 1,936 (209)

Simulation of tungsten target erosion and tungsten impurity transport during argon seeding on EAST

Plasma Physics and Controlled Fusion, 2021
Abstract The upgrade of experimental advanced superconducting tokamak lower divertor to use tungsten (W) target is undertaken, however the target erosion and W impurity accumulation in the core pose a great challenge during high power discharge with external impurity seeding. This paper aims to study the influence
Yilin Wang, Chaofeng Sang, Xuele Zhao
exaly   +2 more sources

Transport analysis of tungsten impurity in ITER

Journal of Nuclear Materials, 2003
Abstract The radial distribution of tungsten impurity in ITER is calculated by using the 1.5D transport code TOTAL coupled with NCLASS, which can solve the neo-classical impurity flux considering arbitrary aspect ratio and collisionality. An impurity screening effect is observed when the density profile is flat and the line radiation power is smaller
Y. Murakami, T. Amano, K. Shimizu, M. Shimada   +3 more
exaly   +2 more sources

Systematic Study of Tungsten Impurity Transport in Representative Regimes of Divertor Plasma

Contributions To Plasma Physics, 2014
AbstractThe tungsten impurity transport has been studied by IMPGYRO code for a model tokamak geometry of JT‐60U tungsten experiments. The background plasma profiles calculated from SOLPS has been used. The density profiles of tungsten are compared between the low background deuterium density (Case A: n = 2.0 × 1019 m–3 at core side boundary) and the ...
K Hoshino, M Toma, Y Homma
exaly   +3 more sources

Tungsten injector for scrape-off layer impurity transport experiments in the Tore Supra tokamak

Review of Scientific Instruments, 2013
This paper describes the design and operation of a new tungsten (W) injection system for impurity transport experiments in the Tore Supra tokamak. The system is mounted on a reciprocating manipulator and injects a controlled amount of gaseous tungsten hexacarbonyl, W(CO)6 at arbitrary depth in the scrape-off layer, using an inertially activated valve ...
M Kočan, J P Gunn, J -Y Pascal
exaly   +4 more sources

Modelling of plasma-wall interaction and impurity transport in fusion devices and prompt deposition of tungsten as application

Plasma Physics and Controlled Fusion, 2017
Abstract Main processes of plasma-wall interaction and impurity transport in fusion devices and their impact on the availability of the devices are presented and modelling tools, in particular the three-dimensional Monte-Carlo code ERO, are introduced.
A Kirschner, D Tskhakaya, S Brezinsek, D Borodin, J Romazanov, R Ding, A Eksaeva, Ch Linsmeier   +7 more
core   +3 more sources

Modelling of tungsten impurity edge transport and screening for different divertor conditions in EAST

Nuclear Fusion, 2022
Abstract Tungsten (W) transport and screening in the edge plasma are investigated for EAST high dissipative divertor conditions. By combining the 1D impurity fluid model (1DImpFM) and the two-point model formatting (2PMF), W screening is proved to be enhanced for high upstream plasma density conditions, mainly because the impurity ...
Hui Wang, Guoliang Xu, Rui Ding, Xiaoju Liu, Hang Si, Qing Zhang, Fang Ding, Dahuan Zhu, Rong Yan, Hai Xie, Lingyi Meng, Liang Wang, Ran Hai, Zhibin Wang, Junling Chen   +14 more
openaire   +1 more source

Neoclassical transport analysis of high rotational trace limit tungsten impurities in KSTAR tokamak

Physics of Plasmas, 2022
The accumulation of tungsten impurities measured in a KSTAR experiment was analyzed theoretically using a drift-kinetic code, NEO, to determine the contribution of neoclassical transport. According to the NEO simulation results, there is a certain value of impurity toroidal rotation speed maximizing the neoclassical inward convection.
Hyojong Lee, Hyeonjun Lee, Yoon Seong Han, Jiheon Song, E. A. Belli, Wonho Choe, Jisung Kang, Jekil Lee, J. Candy, Jungpyo Lee   +9 more
openaire   +1 more source

Effects of impurity transport and melt layer motion to the tungsten wall erosion during anomaly events

Journal of Nuclear Materials, 2015
Abstract Developing designs of future fusion devices, safety and soundness of the rector at anomaly events must be ensured. A computational approach is being taken by developing a homegrown integrated reactor simulation code and analyzing a loss-of-cooling-gas-puff accident (LCGA). This code currently includes simple plasma, edge, and wall models. In
K. Ibano, T. Tsutsui, T.L. Lang, S. Togo, Y. Ogawa   +4 more
openaire   +1 more source

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.
Qingrui 庆瑞 ZHOU 周, Yanjie 彦杰 ZHANG 张, Chaofeng 超峰 SANG 桑, Jiaxian 佳鲜 LI 李, Guoyao 国尧 ZHENG 郑, Yilin 艺霖 WANG 王, Yihan 亦晗 WU 吴, Dezhen 德真 WANG 王   +7 more
openaire   +1 more source

The transport and radiation loss of tungsten impurities in core plasma for the CFEDR conventional H-mode scenario

Plasma Science and Technology
Abstract Impurity transport in the China Fusion Engineering Demo Reactor (CFEDR) conventional H-mode scenario is investigated self-consistently with physics-based core transport. A workflow composed of integrated modeling of the main plasma, the impurity transport calculation module and the radial distribution calculation module has been
Chengxi 呈熙 ZHOU 周, Ling 凌 ZHANG 张, Jiale 佳乐 CHEN 陈, Xiang 翔 JIAN 简, Rui 锐 DING 丁, Vincent CHAN   +5 more
openaire   +1 more source