Plasma installation for research of plasma-surface interaction
DOI:
https://doi.org/10.31489/2019No2/36-42Keywords:
plasma, plasma installation, tungsten, beryllium, irradiationAbstract
This work describes some of the features of the developed plasma setup for studying surface-plasma interactions. Results of the study of the interaction of tungsten and beryllium with plasma are presented. This facility is intended for testing materials and equipment of the Kazakhstan Materials Science Tokomak and for conducting a study of plasma-surface interactions. The main elements of a plasma installation are an electron beam gun, a plasma-beam discharge chamber, a vacuum interaction chamber, a cooled target device, an electromagnetic system consisting of electromagnetic coils, a lock device for quick changing and moving diagnostic tools or irradiated samples without depressurization of the installation. Experiments to study changes in the structure of tungsten and beryllium during plasma exposure have shown that after irradiation, the surface is subjected to erosion and pores form on the surface.
References
"1 Pitts R.A., Carpentier S., Escourbiac F., Hirai T., Komarov V., LisgoS., et al.A full tungsten diverter for ITER: physics issues and design status. J. Nucl. Mater.2013, Vol.438, pp. 48 – 56.
PhilippsV.Tungsten as material for plasma-facing components in fusion devices.Ibid, 2011, Vol.415, pp.2 – 9.
Shimada M., Pitts R., Loarte A., Campbell D.J., Sugihara M., Mukhovatov V., Kukushkin A., Chuyanov V. ITER research plan of plasma–wall interaction. Ibid, 2009, Vol.390-391, pp. 282 – 285.
Ueda Y., Coenen J.W., Temmerman G. De, Doerner R.P., Linke J., Philipps V., Tsitrone E. Research status and issues of tungsten plasma facing materials for ITER and beyond. Fusion Eng. Des., 2014, Vol.89, pp. 901–906.
Federici G., Skinner C. H., Brooks J. N., et al. Plasma-material interactions in current tokamaks and their implications for next step fusion reactors. Nucl. Fusion, 2001, Vol.41, pp. 1967 – 2137.
Tobita K., Nishio S., Enoeda M., et al. Design study of fusion DEMO plant at JAERI.Fusion Eng., 2006, Vol.81, pp. 1151 – 1158.
Suchugov D. Yu., Shapovalov G. V., Chektybaev B. Zh., Skakov M. K., et al. The numerical code TOKSCEN for modeling plasma evolution in Tokomaks. Nuclear Fusion, 2015, No. 55, pp. 1 – 5.
Kurnaev V., Kolodeshnikov A., Tulenbergenov T., Sokolov I. Investigation of plasma–surface interaction at plasma beam facilities. Journal of Nuclear Materials, 2015, Vol.463, pp. 228 – 232.
Rakhadilov B. К.,Skakov M.K., TulenbergenovT.R., WielebaW.K. Change the tungsten surface when irradiated by plasma beam. Bulletin of the Karaganda University. Physics Series.2016, No. 3, pp. 40-44. [in Russian].
Kulsartov T.V., Tazhibaeva I.L., Gordienko YU.N., ZaurbekovaZh.A., Koyanbaev E.T., Kukushkin I.M., Kenzhin E.A., Mukanova A.O., Dyusambaev D.S., Shajmerdenov A.A., Chekushina L.V. Detritiation of different irradiated beryllium grades using high-temperature degassing method. VANT. Ser. Termoyadernyjsintez, 2014, No. 2, pp. 27 – 37. [in Russian].
Rahadilov B.K., Skakov M.K., Tulenbergenov T.R. Tungsten surface erosion by hydrogen plasma irradiation. Key Engineering Materials, 2017, Vol. 736, pp. 46 – 51.
Tulenbergenov T., Skakov M., Kolodeshnikov A., Zuev V., Rakhadilov B., Sokolov I., Ganovichev D.,Miniyazov A., Bukina O. Interaction between nitrogen plasma and tungsten. Nuclear Materials and Energy. 2017, No. 13, pp. 63 – 67.
Skakov M.K., Rakhadilov B.K., Tulenbergenov T.R. Installation for modeling the interaction of plasma with candidate materials of a fusion reactor. Patent of the RK for utility model, No. 2221, Bull.11, publ. 15.06.2017.
Tulenbergenov T.R., Kulsartov T.V., Sokolov I.A., Rakhadilov B.K., Ganovichev D.A., Miniyazov A.J., Sitnikov A.A. Studies on gas release from pre-saturated samples on a plasma beam installation. Physical Sciences and Technology, 2017, Vol. 4, No. 2, pp. 9 – 14.
"