Results 21 to 30 of about 35,628 (303)
Tritium Removal from Carbon Plasma Facing Components [PDF]
Tritium removal is a major unsolved development task for next-step devices with carbon plasma-facing components. The 2-3 order of magnitude increase in duty cycle and associated tritium accumulation rate in a next-step tokamak will place unprecedented ...
Federici, G. +2 more
core +1 more source
High Heat Flux Interactions and Tritium Removal from Plasma Facing Components by a Scanning Laser [PDF]
A new technique for studying high heat flux interactions with plasma facing components is presented. The beam from a continuous wave 300 W neodymium laser was focused to 80 W/mm2 and scanned at high speed over the surface of carbon tiles.
Gentile, C. A. +2 more
core +1 more source
Liquid lithium wettability studies on novel zirconium-alloyed porous tungsten
Liquid lithium wettability has been investigated on novel zirconium-alloyed porous tungsten fabricated by the place-holder spark plasma sintering technique.
C. López Pérez +4 more
doaj +1 more source
Linear plasma device GyM for plasma-material interaction studies
GyM is a linear plasma device operating at Istituto per la Scienza e Tecnologia dei Plasmi, Consiglio Nazionale delle Ricerche, Milan, with the original aim of studying basic plasma physics, such as turbulent processes.
Andrea Uccello +22 more
doaj +1 more source
Study the erosion of Eurofer-97 steel with the linear plasma device GyM
This work reports on the investigation of Eurofer-97 erosion behaviour when exposed to the deuterium plasma of the linear device GyM. The erosion dependence of Eurofer-97 on the deuterium ion fluence, Φ≤2.3×1025 m−2, and temperature of the samples, T ...
Andrea Uccello +9 more
doaj +1 more source
Integrated modelling of the edge plasma and plasma facing components [PDF]
Modelling of the interaction between the edge plasma and plasma facing components (PFCs) has tended to place more emphasis on either the plasma or the PFCs. Either the PFCs do not change with time and the plasma evolution is studied, or the plasma is assumed to remain static and the detailed interaction of the plasma and the PFCs are examined, with no ...
Coster, D. P. +4 more
openaire +4 more sources
W7-X completed its plasma operation in hydrogen with island divertor and inertially cooled test divertor unit (TDU) made of graphite. A substantial set of plasma-facing components (PFCs), including in particular marker target elements, were extracted ...
Rasinski, M. +67 more
core +1 more source
Tungsten fibre-reinforced composites for advanced plasma facing components
The European Fusion Roadmap foresees water cooled plasma facing components in a first DEMO design in order to provide enough margin for the cooling capacity and to only moderately extrapolate the technology which was developed and tested for ITER.
R. Neu +9 more
doaj +1 more source
Assessment of plasma power deposition on the ITER ICRH antennas
Ion cyclotron resonance heating (ICRH) is one of the three additional heating schemes to be deployed on ITER. Its two antenna arrays, installed on the outboard midplane, will deliver 20 MW of RF power in the 40–55 MHz frequency range.
M. Brank +8 more
doaj +1 more source
Fusion tritons and plasma-facing components in a fusion reactor [PDF]
We would like to discuss the role that 1 MeV tritons produced in deuterium$\hbox{--} $deuterium fusion reactions might play in a long-pulse or steady-state fusion reactor.
T. Kurki-Suonio +13 more
core +1 more source

