Open AccessTests of tungsten divertor mock-ups with plasma and e-beam high-heat fluxes
Author(s) -
В. П. Будаев,
А. В. Дедов,
A. T. Komov,
A. N. Varava,
П. Г. Фрик,
S. D. Fedorovich,
R. Giniyatulin,
A. Makhankov,
N.V. Litunovsky,
A. V. Zakharenkov,
E. V. Sviridov,
I A Tupotilov,
Brant Chang
Publication year - 2019
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/1383/1/012017
Subject(s) - divertor , tungsten , plasma , beam (structure) , heat load , nuclear engineering , materials science , helium , transient (computer programming) , atomic physics , nuclear physics , physics , tokamak , thermodynamics , optics , metallurgy , computer science , engineering , operating system
The tungsten divertor mock-ups were tested with high-heat fluxes in the e-beam facility and in the plasma device. The water-cooled mock-ups are tested with the combination of plasma and e-beam loads: (1) thermocyclic tests with the highpower electron beam load ranging from 5 to 40 MW/m 2 and then (2) tests in the PLM plasma device with stationary plasma loads of up to 5 MW/m 2 . Such two tests are performed together for the first time. They simulate the variable loads onto the divertor plates, which can occur in the ITER during stationary discharges with transient ELM events. The duration of helium plasma discharges in the PLM amounted to 200 minutes. The temperature of the test targets heating amounted to 1000°C and more.