Results 221 to 230 of about 18,332 (234)
Some of the next articles are maybe not open access.
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 +4 more
openaire +1 more source
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 +4 more
openaire +1 more source
Contributions To Plasma Physics
AbstractTungsten (W) impurity eroded from the divertor target can degrade the confinement performance of future fusion reactors. The mechanism of the effect of E × B drift on the W transport in the scrape‐off layer (SOL) was investigated with a fixed cross‐field anomalous particle diffusion coefficient for W ions (D⊥,W) of 1 m2s−1 in our previous ...
Jin Guo, Shifeng Mao, Guoliang Xu
exaly +2 more sources
AbstractTungsten (W) impurity eroded from the divertor target can degrade the confinement performance of future fusion reactors. The mechanism of the effect of E × B drift on the W transport in the scrape‐off layer (SOL) was investigated with a fixed cross‐field anomalous particle diffusion coefficient for W ions (D⊥,W) of 1 m2s−1 in our previous ...
Jin Guo, Shifeng Mao, Guoliang Xu
exaly +2 more sources
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 +7 more
openaire +1 more source
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 +7 more
openaire +1 more source
Effects of Tungsten Radiative Cooling on Impurity, Heat and Momentum Transport in DIII-D Plasmas
A first-of-its-kind experiment was conducted in the DIII-D tokamak under WEST similarity constraints on plasma shape and core parameters. This work presents a detailed transport study comparing a reference regime dominated by intrinsic carbon radiation and a high-radiation regime resulting from controlled tungsten (W) injection using the Laser Blow-OffBiwole, A. Tema +23 more
openaire +1 more source
On the influence of tungsten impurities on the transport properties of thermal plasma
2011???????????????????? ?????????? ?????????????? ?????????????????? ???? ?????????????????????? ?????????????????????? ?????????????????? ???????????? ?? ?????????????????? ????????????. ?????????????????? ???????????????????? ???????????????????????? ???? ???????????? ???????????????? ??????????. ????????????????, ???? ???????????????? ??????????????????
openaire +1 more source
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 +5 more
openaire +1 more source
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 +5 more
openaire +1 more source
OEDGE modeling of far-SOL tungsten impurity sources and screening in WEST
Nuclear Materials and Energy, 2022West Team
exaly
Global modelling of tungsten impurity transport based on the drift-kinetic equation
Nuclear Fusion, 2020Ryûtarô Kanno, G Kawamura, M Nunami
exaly