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Influence of the Carbidized Tungsten Surface on the Processes of Interaction with Helium Plasma.
Skakov, Mazhyn; Miniyazov, Arman; Batyrbekov, Erlan; Baklanov, Viktor; Koyanbayev, Yerbolat; Gradoboev, Aleksandr; Kozhakhmetov, Yernat; Sokolov, Igor; Tulenbergenov, Timur; Zhanbolatova, Gainiya.
Afiliação
  • Skakov M; National Nuclear Center of the Republic of Kazakhstan, Kurchatov 071100, Kazakhstan.
  • Miniyazov A; Institute of Atomic Energy Branch of the National Nuclear Center of the Republic of Kazakhstan, Kurchatov 071100, Kazakhstan.
  • Batyrbekov E; Faculty of Engineering and Technology, Shakarim University, Semey 070000, Kazakhstan.
  • Baklanov V; National Nuclear Center of the Republic of Kazakhstan, Kurchatov 071100, Kazakhstan.
  • Koyanbayev Y; Institute of Atomic Energy Branch of the National Nuclear Center of the Republic of Kazakhstan, Kurchatov 071100, Kazakhstan.
  • Gradoboev A; Institute of Atomic Energy Branch of the National Nuclear Center of the Republic of Kazakhstan, Kurchatov 071100, Kazakhstan.
  • Kozhakhmetov Y; Department of Experimental Physics, Tomsk Polytechnic University, 634050 Tomsk, Russia.
  • Sokolov I; Institute of Atomic Energy Branch of the National Nuclear Center of the Republic of Kazakhstan, Kurchatov 071100, Kazakhstan.
  • Tulenbergenov T; Institute of Atomic Energy Branch of the National Nuclear Center of the Republic of Kazakhstan, Kurchatov 071100, Kazakhstan.
  • Zhanbolatova G; Faculty of Engineering and Technology, Shakarim University, Semey 070000, Kazakhstan.
Materials (Basel) ; 15(21)2022 Nov 05.
Article em En | MEDLINE | ID: mdl-36363413
ABSTRACT
This paper presents the results of experimental studies of the interaction of helium plasma with a near-surface tungsten carbide layer. The experiments were implemented at the plasma-beam installation. The helium plasma loading conditions were close to those expected in the ITER divertor. The technology of the plasma irradiation was applied in a stationary type linear accelerator. The impact of the helium plasma was realized in the course of the experiment with the temperatures of ~905 °C and ~1750 °C, which were calculated by simulating heat loading on a tungsten monoblock of the ITER divertor under the plasma irradiation at the load of 10 MW/m2 and 20 MW/m2, respectively. The structure was investigated with scanning microscopy, transmitting electron microscopy and X-ray analysis. The data were obtained showing that the surface morphology changed due to the erosion. It was found that the carbidization extremely impacted the plasma-tungsten interaction, as the plasma-tungsten interaction with the carbide layer led to the carbon sputtering and partial diffusion towards to the depth of the sample. According to these results, WC-based tungsten carbide is less protected against fracture by helium than W and W2C. An increase in temperature leads to much more extensive surface damage accompanied by the formation of molten and recrystallized flanges.
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Texto completo: 1 Coleções: 01-internacional Base de dados: MEDLINE Idioma: En Revista: Materials (Basel) Ano de publicação: 2022 Tipo de documento: Article País de afiliação: Cazaquistão

Texto completo: 1 Coleções: 01-internacional Base de dados: MEDLINE Idioma: En Revista: Materials (Basel) Ano de publicação: 2022 Tipo de documento: Article País de afiliação: Cazaquistão