Конференции НИЯУ МИФИ

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Просмотр Конференции НИЯУ МИФИ по Автор "Borodin, D."

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    ANALYTICAL EXPRESSION FOR THE SHEATH ELECTRIC FIELD FOR SPUTTERING MODELLING AT JET ILW EXPERIMENTS
    (НИЯУ МИФИ, 2017) Borodkina, I.; Borodin, D.; Brezinsek, S.; Tsvetkov, I. V.; Kurnaev, V. A.; Klepper, C. C.; Lasa, A.; Guillemaut, C.; Jacquet, P.; Stamp, M. F.; Giroud, C.
    The study of plasma–surface interaction processes is important for a successful realization of the international ITER project. The JET ITER-like wall (ILW) [1] comprises a tungsten (W) divertor and beryllium (Be) main chamber wall thus matching the material configuration planned for ITER. Estimating plasma facing component (PFC) sputtering by plasma ions is an important issue for ITER as erosion determines the life time of PFC, impacts on the tritium retention by co-deposition with Be and leads to an increase of impurities in core plasma and the consequent reduction in fusion plasma performance. For correct calculation of the sputtering yields for PFCs the accurate expression for the sheath electric field must be included. This work represents the review of our previous works devoting to the development of analytical expressions for the sheath electric field taking into account the presence of an oblique magnetic field, secondary electron-electron emission and surface biasing.
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    ERO-PSI CODE FOR NUMERICAL SIMULATION OF EXPERIMENTS ON TUNGSTEN SPUTTERING IN LINEAR PLASMA DEVICE PSI-2
    (НИЯУ МИФИ, 2015) Eksaeva, A. A.; Marenkov, E. D.; Borodin, D.; Kirshner, A.; Laenger, M.; Kurnaev, V. A.; Kreter, A.; Маренков, Евгений Дмитриевич
    Plasma-wall interaction is one of the recognized issues for thermonuclear reactor performance and seems to be a key direction in fusion researches in the framework of the ITER project [1]. Tungsten (W) has been chosen as a main material for construction of ITER divertor due to its low sputtering at edge plasma temperatures, large melting temperature, and small uptake of tritium.