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Просмотр Взаимодействие плазмы с поверхностью по Автор "BORODIN, D."
(НИЯУ МИФИ, 2018) BORODKINA, I.; DOUAI, D.; BORODIN, D.
The Joint European Torus (JET) is the largest tokamak in use and currently the only one capable of handling tritium (T). JET equipped with the ITER-like wall (ILW) utilizing the same as ITER material combination: tungsten (W) divertor and beryllium (Be) main chamber, provides the most relevant environment for ITER plasma-wall interaction studies. In 2017 the coordinated on-site and off-site analysis and modelling activities in the frame of the fifteen researcher groups named as “analysis&modelling tasks” were performed: analysis of past experiments & assess of JET D-T campaign readiness, predictive modelling with physics based integrated (edge-core, wall-SOL) codes for JET and ITER, preparation of experimental proposals for C38- C42 D-H-T-H-D upcoming campaigns.
(НИЯУ МИФИ, 2016) BORODKINA, I.; BORODIN, D.; BREZINSEK, S.; TSVETKOV, I. V.; KURNAEV, V. A.; KLEPPER, C. C.; LASA, A.; KRETER, A.; Цветков, Игорь Владимирович
Understanding plasma-surface interaction (PSI) processes is important for the successful realization of the ITER project. PSI processes are determined to a large extent by the Debye sheath and magnetic pre-sheath effects. For the cor-rect calculation of ions trajectories just before the surface impact and in the presence of the oblique magnetic field, it is necessary to include the precise sheath electric field distribution. Furthermore, in a number of experiments the surface biasing up to several hundred Volt is applied to the plasma facing com-ponents (PFC) that also influences greatly the sheath potential.