TCV divertor upgrade for alternative magnetic configurations [PDF]
Nuclear Materials and Energy, 2017 The Swiss Plasma Center (SPC) is planning a divertor upgrade for the TCV tokamak. The upgrade aims at extending the research of conventional and alternative divertor configurations to operational scenarios and divertor regimes of greater relevance for a ...
H. Reimerdes +20 more
doaj +3 more sources
Radiation characteristics of detached divertor plasmas in W7-X
Nuclear Materials and Energy, 2022 Detached divertor plasmas has been achieved by density ramp in W7-X. During the transition into detachment, the main divertor radiation region moves from the region close to the divertor targets to the region around LCFS.
E. Wang +16 more
doaj +1 more source
Modeling of argon seeding in ASDEX Upgrade H-mode plasma with SOLPS5.0
Nuclear Materials and Energy, 2017 SOLPS modeling of Ar seeding in ASDEX Upgrade H-mode plasma shows that the divertor compression of Ar increases with the seeding rate when the inner divertor is detached and the outer divertor is attached.
L.Y. Xiang +6 more
doaj +1 more source
Island divertor configuration design for a quasi-axisymmetric stellarator CFQS [PDF]
, 2020 0000-0002-8156-8233A magnetic field configuration of an island divertor for a quasi-axisymmetric stellarator (CFQS) is proposed. The configuration incorporates large islands surrounding the core confinement region.
LIU, Haifeng +6 more
core +1 more source
R&D on divertor plasma facing components at the Institute for Plasma Research
Nukleonika, 2015 This paper is focused on various aspects of the development and testing of water cooled divertor PFCs. Divertor PFCs are mainly designed to absorb the heat and particle fluxes outflowing from the core plasma of fusion devices like ITER.
Patil Yashashri +6 more
doaj +1 more source
Effect of divertor legs on neutral particle and impurity retention for a closed helical divertor configuration in the Large Helical Device [PDF]
, 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 +5 more
core +1 more source
The impact of ELMs on the ITER divertor [PDF]
, 1998 Edge-Localized-Modes (ELMs) are expected to present a significant transient flux of energy and particles to the ITER divertor. The threshold for ablation of the graphite target will be reached if the ELM transient exceeds Q/t{sup 1/2} {approximately} 45 ...
Herrmann, A. +9 more
core +1 more source
Simulation Analysis of the Design of a Vacuum Pumping System for the Closed Helical Divertor in the Large Helical Device [PDF]
, 2011 A promising candidate of a vacuum pumping system for the closed helical divertor in the large helical device is proposed using a three-dimensional neutral particle transport simulation code (EIRENE) and a finite element based multi-physics analysis ...
MORISAKI, Tomohiro +7 more
core +1 more source
Density dependence of SOL power width in ASDEX upgrade L-Mode
Nuclear Materials and Energy, 2017 Understanding the heat transport in the scrape-off layer (SOL) and the divertor region is essential for the design of large fusion devices such as ITER and DEMO.
B. Sieglin +6 more
doaj +1 more source
On the lifetime of the first mirrors in the diagnostic systems of the international thermonuclear experimental reactor [PDF]
, 2006 Plasma diagnostic systems will be necessary tools for the future success of the International Thermonuclear Experimental Reactor (ITER) both to better understand the physics involved in magnetically confined burning plasma and for the protection of the
Temmerman, Gregory de
core +1 more source