High-heat flux tests of tungsten divertor mock-ups with steady-state plasma and e-beam

V.P. Budaev,S.D. Fedorovich,A.V. Dedov,A.V. Karpov,A.T. Komov,Yu.V. Martynenko,R.N. Giniyatulin,A.N. Makhankov, N.V. Litunovsky,A.P. Sliva,A. Yu. Marchenkov, D.N. Gerasimov, M.K. Gubkin,M.V. Lukashevsky, A.V. Zakharenkov, A.V. Lazukin, G.B. Vasiliev

Nuclear Materials and Energy（2020）

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摘要

•Mock-ups of the ITER tungsten divertor plate were tested with the combination of thermocyclic electron beam tests of up to 40 MW/m2 and subsequently with steady-state plasma of 0.5–1 MW/m2 in the PLM plasma device.•The tests led to erosion, cracking, and nanostructured “fuzz” growth on the tungsten surface.•The “fuzz” layer on tungsten surface was tested with the e-beam.

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关键词

High-heat flux test,Plasma-facing materials,Tungsten,ITER,Fusion reactor

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