Our research group is dedicated to the study and detailed investigation of fusion-relevant (FR) PFMs using calibration-free LIBS (CF-LIBS). Laser-Induced Breakdown Spectroscopy (LIBS) has been found the most promising analytical technique among the few already established techniques, for the quantitative and depth profile study of PFMs, and is being considered to be installed in international thermonuclear experimental reactor (ITER) in the form of a robotic arm. Owing to its advantages, i.e., in-situ analysis, online monitoring, and fast analysis, etc. Also, the choice of plasma-facing materials (PFMs) is a major concern. New approaches, like neural networks, can help in solving complicated problems in time scales unattainable before.Ībstract: In view of the safe and successful operation of future fusion devices, it is highly important to determine the quantity of retained fuel in the plasma-facing components (PFCs). This grants us certain benefits in magnetic confinement of plasma, but most of the algorithms cannot achieve the required speed. There is also another level of fast computations, when we try to obtain the results in real time. This eventually gives better results than just improving the basic physical model. ![]() There are cases, when reducing the complexity of the models, which allows us to include more phenomena into our computation code. The key issue is computation time, which is usually the main constraint on the usability of the model in practical application. As unintuitive it might be, sometimes the way to the result which more accurately reflects reality is not by developing more accurate models, but by finding their approximations. Therefore, without dedicated computation tools it would not be possible to carry on with the fusion project. It involves so many phenomena, that it is extremely difficult, from the computation point of view, to obtain reliable results in a reasonable time. Verification and validation of this new spectral filament model is detailed, with implications for plasma wall interaction in tokamak reactors.Ībstract: Plasma physics is probably one of the most complicated fields to deal with. Another point of view was adopted: what about describing those blobs as an assembly of spatial wave packets parametrized by wave spectra? It turns out that theoretical models for isolated blob dynamics can be adapted to models predicting the time averaged amplitude and shape of density and potential spectra. Yet, moving from isolated blob models to macroscopic transport models does require statistical laws for blobs that do not exist yet. ![]() This was carried on a large dataset collected in the Tore Supra tokamak, featuring simple circular geometry, and revealed a sound agreement with predictions. Experimental investigations generally focus on constructing averaged blob observables, like shape, amplitude and propagation speeds, because those quantities can be directly compared to theoretical predictions for isolated blobs. ![]() The aim of this work is to advance our understandings of the dominant transport mechanism in the central region (r/a 0.3, where much of the work has already been done previously.Ībstract: At the boundary of tokamak or stellarators plasmas, transport across magnetic confinement is generally associated to the intermittent propagation of isolated filaments, or blobs, considered ruling plasma wall interaction. Transport of tungsten (W) in the central part of ITER (r/a 0.3) and the central part remains relatively unexplored so far. However, tokamaks operation with metallic plasma-facing components raises issues regarding the control of high-Z impurities since the accumulation of heavy impurities such as tungsten (Z=74) in the plasma core leads to significant radiation losses and deteriorates the energy confinement. In ITER, metallic plasma-facing components are chosen for their low tritium retention and ability to sustain high heat loads. Abstract: One of the major goals of the ITER project is to demonstrate high fusion power gain in a tokamak.
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