Analysis of the beryllium stability under standard and critical operation in a fusion reactor

Sokolov I.A. Skakov M.K. Miniyazov A.Z. Aubakirov B.T. Tulenbergenov T.R. Gradoboev A.V.
2021 L.N. Gumilyov Eurasian National University

Eurasian Journal of Physics and Functional Materials
2021 #5 Issue 4 188 - 197 pp.

The paper provides data on the peculiarity of change in the structure, structural phase changes and destructions in beryllium resulting from interaction with a near-wall plasma of fusion facilities. Beryllium resistance under conditions of ITER operation was evaluated, which considers factors leading to possible partial melting and erosion of panels of the ITER first wall. It presents the modelling of a heat s distribution in element (“finger”) of the first wall at “normal” and “increased” heat flux of the ITER operation.

beryllium , electron beam , fusion , heat load , hydrogen , ITER , plasma , Tokamak

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Institute of Atomic Energy Branch RSE NNC RK, Kurchatov, Kazakhstan
National Nuclear Center of the Republic of Kazakhstan, Kurchatov, Kazakhstan
Tomsk Polytechnic University, Tomsk, Russian Federation

Institute of Atomic Energy Branch RSE NNC RK
National Nuclear Center of the Republic of Kazakhstan
Tomsk Polytechnic University

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