Results 261 to 270 of about 35,628 (303)

Damage modelling in plasma facing components

Journal of Nuclear Materials, 2009
Abstract The plasma facing components of controlled fusion devices are submitted to high heat fluxes in operating conditions (from 10 to 20 MW/m 2 ). These components are made of a carbon/carbon composite tile bonded to a copper alloy heat sink. Due to the thermal expansion mismatch between the composite and the copper alloy, significant stresses may
E. Martin, G. Camus, J. Schlosser, G. Chevet   +3 more
openaire   +1 more source

Tritium in plasma facing components

Nuclear Fusion, 1992
Report on the Workshop held after the 10th PSI Conference, Livermore, California, United States of America, 6-7 April 1992.
openaire   +1 more source

Effect of disruptions on plasma-facing components

Proceedings of 16th International Symposium on Fusion Engineering, 2002
Erosion of plasma-facing components during disruptions is a limiting factor in the design of large tokamaks like ITER. During a disruption, much of the stored thermal energy of the plasma will be dumped onto divertor plates, resulting in local heat fluxes, which may exceed 100 GW/m/sup 2/ over a period of about 0.1-1.0 msec.
J.G. Gilligan, M.A. Bourham, E.C. Tucker
openaire   +1 more source

Development of plasma facing components at JAERI

Fusion Engineering and Design, 1991
The development and design of the divertor plate in JAERI are presented. Small divertor models are fabricated and tested in an electron beam heating facility in the JAERI. Typical heat load is 10 MW/m2. The divertor models consist of CFC or isotropic graphite/Cu bonded structures. A twisted tape is inserted to enhance heat transfer.
M. Akiba, H. Takatsu, T. Kuroda, H. Hashizume, M. Araki, M. Dairaku, H. Ise, S. Suzuki, S. Tanaka, K. Yokoyama, M. Seki   +10 more
openaire   +1 more source

Lithium as a plasma facing component to optimize the edge plasma

2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 2015
The use of lithium to coat plasma-facing components (PFCs) or serve directly as liquid PFCs has resulted in energy confinement improvement in several devices. Coupled with the demonstrated ability of liquid Li to exhaust high power fluxes, the use of Li could resolve the two leading problems of high-Z PFCs. The effect of Li in NSTX, EAST, and DIII-D is
R. Maingi, R. Majeski, J.E. Menard, M.A. Jaworski, R. Kaita   +4 more
openaire   +1 more source

Plasma Interactions with Mixed-Material Plasma Facing Components

Physica Scripta, 1999
The interactions of several types of mixed-materials with a bombarding deuterium plasma are described in this paper. The first type of mixed-material surface is a designed, or engineered, surface: a silicon-doped carbon-fiber composite (NS-31). The Si-doped CFC is compared to an identical, but undoped CFC.
R. P. Doerner, S. C. Luckhardt, R. Seraydarian, F. C. Sze, D. G. Whyte   +4 more
openaire   +1 more source

Investigation of Plasma Facing Components in Plasma Focus Operation

Journal of Fusion Energy, 2006
Both aspects of the plasma–wall interactions, counter effect of plasma and materials, have been considered in our experiments. The AEOI plasma focus, Dena, has Filippov-type electrodes. The experimental results verify that neutron production increases using tungsten as an anode insert material, compared to the copper one. The experiments show decrement
M. V. Roshan, A. R. Babazadeh, S. M. Sadat Kiai, H. Habibi, M. Mamarzadeh   +4 more
openaire   +1 more source

Development of Carbon Materials and Plasma Facing Components for ITER

Physica Scripta, 2004
A significant R&D effort was carried out in EU to develop suitable CFC materials with a three-directional fibre structure. The main goal was to obtain a high thermal conductivity, which is required to remove the expected heat load with a sacrificial thickness of at least 15?20 mm, with a proper balance of the mechanical properties.
Merola, M., Wu, C., EU ITER Participating Team   +2 more
openaire   +2 more sources

RUNAWAY ELECTRONS ON PLASMA FACING COMPONENTS

1993
Runaway electrons can cause severe damage to plasma facing components of large tokamaks. The designs proposed for the first wall and divertor of the next large fusion experiment, ITER (International Thermonuclear Experimental Reactor), are investigated. Energies of up to 300 MeV per electron and surface energy depositions of 30 MJ/m2 are assumed.
openaire   +2 more sources

The Design of Actively Cooled Plasma-Facing Components

Physica Scripta, 2001
In future fusion devices, like in the stellarator Wendelstein 7-X, the target plates of the divertor will be exposed to heat loads up to power densities of 10 MW/m2 for 1000 s. For this purpose actively cooled target elements with an internal coolant flow return, made of 2-D CFC armor tiles brazed onto a two tube cooling structure were developed and ...
Scheerer, M., Bolt, H., Gervash, A., Linke, J., Smid, I.   +4 more
openaire   +2 more sources