Results 11 to 20 of about 812,697 (276)

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

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 ...
Gruber, O., Herrmann, A., Laux, M., Mertens, V., Rohde, V., Haas, G., Yoon, S. W., Pütterich, T., Neu, R., Eich, T., Gafert, J., Kaufmann, M., Neuhauser, J., Yoon, S., ASDEX Upgrade Team, Stober, J., Ryter, F., Maggi, C., Müller, H. W., Fuchs, J. C., Fuchs, J., Müller, H., Kallenbach, A.   +22 more
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Design of a Closed Helical Divertor in LHD and the Prospect for Helical Fusion Reactors [PDF]

Fusion Science and Technology, 2017
A new closed helical divertor configuration for efficient particle control and reduction of the heat load on the divertor plates is proposed. The closed divertor configuration practically utilizes an ergodic layer and magnetic field line configuration on
YAMADA, Hiroshi, the LHD Experimental Groups,, LHD Experimental Groups,, LHD Experimental Group,, SAGARA, Akio, KOMORI, Akio, KOBAYASHI, Masahiro, SHOJI, Mamoru, MASUZAKI, Suguru, the LHD Experimental Group,   +9 more
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Effect of divertor legs on neutral particle and impurity retention for a closed helical divertor configuration in the Large Helical Device [PDF]

Effect of divertor legs on neutral particle and impurity retention for a closed helical divertor configuration in the Large Helical Device, 2011
A closed helical divertor (CHD) has been designed for efficient particle control in the plasma periphery and for retaining neutral particles and impurity ions in the divertor region.
LHD, Experiment Group, MORISAKI, Tomohiko, SHOJI, Mamoru, MASUZAKI, Suguru, SAKAMOTO, Ryuichi, YAMADA, H.   +5 more
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Closed Helical Divertor Experiments [PDF]

Closed Helical Divertor Experiments
departmental bulletin ...
"Morisaki, T., Masuzaki, S., High, Density and Divertor Group"   +2 more
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Investigation of the Helical Divertor Function and the Future Plan of a Closed Divertor for Efficient Particle Control in the LHD Plasma Periphery [PDF]

Fusion Science and Technology, 2009
The function of the divertor plasmas on the particle control in the plasma periphery is investigated from viewpoints of magnetic field line structures and neutral particle transport in the Large Helical Device (LHD).
SAKAUE, A, KOMORI, Akio, IWAMAE, Atsushi, LHD Experiment Group, KOBAYASHI, Masahiro, MORISAKI, Tomohiko, SHOJI, Mamoru, GOTO, Motoshi, MASUZAKI, Suguru, YAMADA, H.   +9 more
core   +2 more sources

Experimental investigation of a closed vapour box module for a divertor-like configuration in Magnum-PSI

Nuclear Fusion
Efficient management of extreme heat fluxes in the divertor region to extend the lifetime of the components remains a critical challenge for the realization of nuclear fusion-based power plants.
Fabio Romano, V.F.B. Tanke, J.A. Schwartz, R.J. Goldston, S. Brons, T.W. Morgan   +5 more
doaj   +2 more sources

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

Study of the effect of a closed divertor configuration on neutral particle control in the LHD plasma periphery [PDF]

, 2009
An optimized closed divertor configuration for effective particle control in LHD is proposed from the viewpoints of the distribution of the strike points and neutral particle transport.
the LHD Experimental Groups,, LHD Experimental Groups,, LHD Experimental Group,, WATANABE, T., Komori, Akio, KOBAYASHI, Masahiro, SHOJI, Mamoru, MASUZAKI, Suguru, the LHD Experimental Group,, YAMADA, H.   +9 more
core   +1 more source

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