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ITER R&D: Auxiliary Systems: Safety Related R&D

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Dust-particle transport in tokamak edge plasmas

TL;DR: A physical model for dust transport simulation and a newly developed code DUSTT are discussed in this article, which incorporates both dust dynamics due to comprehensive dust-plasma interactions as well as the effects of dust heating, charging, and evaporation.
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Transport of dust particles in tokamak devices

TL;DR: In this article, a physical model for dust transport in tokamak devices is presented, as well as modeling results on dynamics of dust particles in plasma and conditions necessary for particle growth in plasma.
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Effects dust size distribution on transportation of dust grains in a weakly ionized plasma

TL;DR: In this paper, the authors studied the transport of charges, mass and heat of dust particles in a weakly ionized plasma, and the dependence of electric conductivity, diffusion coefficient and heat conduction coefficient of the dust particles on total number of particles, number of neutrals, and collision cross section area between dust particles and neutrals.

An overview of results in the ITER generic site safety report (GSSR)

TL;DR: In this paper, the results of the ITER safety assessments during the course of the Engineering Design Activities (EDA) are summarized, including effluents and emissions from normal operation, including planned maintenance activities; occupational safety for workers at the facility; radioactive materials and wastes generated during operation and from decommissioning; and potential incidents and accidents and the resulting transients.
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Journal ArticleDOI

Plasma{material interactions in current tokamaks and their implications for next step fusion reactors

TL;DR: In this article, the authors review the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next-step fusion reactors.
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In-vessel tritium retention and removal in ITER

TL;DR: In this article, the authors present the results of current predictions both in terms of implantation and codeposition rates, and critically discuss their uncertainties and sensitivity to important design and operation parameters such as the plasma edge conditions, the surface temperature, the presence of mixed-materials, etc.
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Tritium retention in tungsten exposed to intense fluxes of 100 eV tritons

TL;DR: The Tritium Plasma Experiment Experiment (TPE) has been used to examine the retention of tritium in tungsten exposed to very high fluxes of 100 eV tritons as mentioned in this paper.
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Hydrogen isotope retention in beryllium for tokamak plasma-facing applications

TL;DR: In this article, the authors review experimental data regarding hydrogenic atom inventories in experiments pertinent to tokamak applications and show that with some very plausible assumptions, the experimental data appear to exhibit rather predictable trends.
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Comparison of the thermal stability of the codeposited carbon/hydrogen layer to that of the saturated implant layer

TL;DR: In this article, the results of an experimental study of the thermal stability in air and vacuum of the codeposited carbon/hydrogen layer formed in a carbon-lined fusion reactor were presented.
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