Results 11 to 20 of about 304 (249)

Evaluation of plasma impurity concentration during radiative divertor operation mode on EAST

He jishu, 2022
BackgroundBy injecting gaseous neon (Ne) or argon (Ar) into the divertor region, the radiative divertor operation mode has been successfully realized on experimental advanced superconducting tokamak (EAST).
JI Huajian, ZHANG Hongming, YANG Xiuda, YIN Xianghui, LI Kedong, HE Liang, FU Jia, WANG Fudi, SHEN Yongcai, WAN Shunkuan, LYU Bo, GONG Xueyu, GONG Xianzu, ZANG Qing, WANG Yumin, LIN Xin, WANG Shouxin   +16 more
doaj   +1 more source

Boron transport simulation using the ERO2.0 code for real-time wall conditioning in the large helical device

Nuclear Materials and Energy, 2020
The three-dimensional Monte-Carlo impurity transport and plasma surface interaction code ERO2.0 is applied to a full-torus model for the Large Helical Device (LHD).
M. Shoji, G. Kawamura, J. Romazanov, A. Kirschner, A. Eksaeva, D. Borodin, S. Masuzaki, S. Brezinsek   +7 more
doaj   +1 more source

The ASDEX Upgrade divertor IIb—a closed divertor for strongly shaped plasmas

Nuclear Fusion, 2003
A new divertor configuration (DIV-IIb) has been implemented in ASDEX Upgrade. In order to accommodate a large variety of plasma shapes with bottom triangularities (δbot) up to 0.48, the outer strikepoint region was modified and the roof baffle was lowered and diminished at its outer part in comparison with the previous divertor (DIV-II). The inner part
Neu, R., Fuchs, J., Kallenbach, A., Maggi, C., Rohde, V., Ryter, F., Eich, T., Gafert, J., Gruber, O., Haas, G., Herrmann, A., Kaufmann, M., Laux, M., Mertens, V., Müller, H., Neuhauser, J., Pütterich, T., Stober, J., Yoon, S., ASDEX Upgrade Team   +19 more
openaire   +3 more sources

Simulation studies of divertor detachment and critical power exhaust parameters for Japanese DEMO design

Nuclear Materials and Energy, 2021
Handling of a large thermal power exhausted from the confined plasma is one of the most important issues for ITER and DEMO. A conventional divertor, which has the closed geometry similar to that of ITER and longer leg of 1.6 m, was proposed for the ...
N. Asakura, K. Hoshino, Y. Homma, Y. Sakamoto   +3 more
doaj   +1 more source

Design of a multi-configurations divertor for the DTT facility

Nuclear Materials and Energy, 2022
The standard positive triangularity H-mode tokamak operation with Single Null Divertor (SND) configuration and tungsten monoblocks targets can face some difficulties in providing a solution scalable towards the realization of the fusion reactor.
P. Innocente, R. Ambrosino, S. Brezinsek, G. Calabrò, A. Castaldo, F. Crisanti, G. Dose, R. Neu, S. Roccella   +8 more
doaj   +1 more source

Comparison of 2D simulations of detached divertor plasmas with divertor Thomson measurements in the DIII-D tokamak

Nuclear Materials and Energy, 2017
A modeling study is reported using new 2D data from DIII-D tokamak divertor plasmas and improved 2D transport model that includes large cross-field drifts for the numerically difficult low anomalous transport regime associated with the H-mode.
T.D. Rognlien, A.G. McLean, M.E. Fenstermacher, M. Groth, A.E. Jaervinen, I. Joseph, C.J. Lasnier, W. Meyer, A. Moser, G.D. Porter, M.V. Umansky   +10 more
doaj   +1 more source

Results from core-edge experiments in high Power, high performance plasmas on DIII-D

Nuclear Materials and Energy, 2017
Significant challenges to reducing divertor heat flux in highly powered near-double null divertor (DND) hybrid plasmas, while still maintaining both high performance metrics and low enough density for application of RF heating, are identified.
T.W. Petrie, M.E. Fenstermacher, C.T. Holcomb, T.H. Osborne, S.L. Allen, J.R. Ferron, H.Y. Guo, C.J. Lasnier, A.W. Leonard, T.C. Luce, M.A. Makowski, A.G. McLean, D.C. Pace, W.M. Solomon, F. Turco, M.A. VanZeeland, J.G. Watkins   +16 more
doaj   +1 more source

Impact of fine divertor geometrical features on the modelling of JET corner configurations

Nuclear Materials and Energy, 2021
The modelling of JET corner configurations, in which the strike points are positioned deep in the corners of the divertor, is extremely challenging for edge plasma fluid modelling tools.
P. Tamain, H. Bufferand, G. Ciraolo, C. Giroud, Y. Marandet, F. Militello, D. Moulton, N. Vianello   +7 more
doaj   +1 more source

Demonstration of suppression of dust generation and partial reduction of the hydrogen retention by tungsten coated graphite divertor tiles in LHD

Nuclear Materials and Energy, 2019
Three sets of tungsten coated graphite divertor tiles (VPS-W tiles) were installed in the closed helical divertor of the Large Helical Device (LHD) instead of the graphite divertor tiles in the 2012FY plasma campaign for examining the plasma wall ...
M. Tokitani, S. Masuzaki, T. Murase
doaj   +1 more source

Energy and particle balance during plasma detachment in a long-leg divertor configuration

Nuclear Fusion, 2023
Comprehensive studies of energy and particle balances in the transition to plasma detachment in an alternative divertor configuration with long outer legs are shown.
R. Masline, S.I. Krasheninnikov
doaj   +1 more source