High-heat flux tests of fusion materials with stationary plasma in the PLM device

•New plasma device was constructed for plasma tests of fusion reactor materials.•Tungsten plates were irradiated with powerful electron beam and plasma.•Erosion and nanostructured fuzz-like structure growth on tungsten after the tests.•Liquid tin metal capillary porous system was tested in steady-st...

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Bibliographic Details
Published in:Fusion engineering and design 2020-06, Vol.155, p.111694, Article 111694
Main Authors: Budaev, Viacheslav Petrovich, Fedorovich, Sergey, Dedov, Alexey, Martynenko, Yuri, Frick, Peter, Karpov, Alexey, Van Oost, Guido, Lyublinsky, Igor, Vertkov, Alexey, Lukashevsky, Mikhail, Gubkin, Mikhail, Marchenkov, Artem, Sviridov, Evgeny, Grashin, Sergey, Lubenchenko, Alexander, Lazukin, Alexander, Sliva, Andrey, Rogozin, Konstantin, Zakletsky, Zakhar
Format: Article
Language:English
Subjects:
Electron beams
Fusion reactor
Heat flux
Heat transfer
High heat flux test
ITER
Lithium
Nuclear engineering
Nuclear power plants
Plasma
Plasma-facing materials
Porous materials
Steady state
Tin
Tokamak devices
Tungsten
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Summary:•New plasma device was constructed for plasma tests of fusion reactor materials.•Tungsten plates were irradiated with powerful electron beam and plasma.•Erosion and nanostructured fuzz-like structure growth on tungsten after the tests.•Liquid tin metal capillary porous system was tested in steady-state plasma.•Lithium materials deposited in tokamak were irradiated with steady-state plasma. The PLM plasma device was constructed for high heat flux tests of fusion plasma-facing materials and in-vessel components of a fusion reactor. The ITER-grade tungsten samples were irradiated with steady-state plasma in PLM. The combined tests of ITER-grade tungsten samples with an e-beam load of 40 MW/m2 and stationary steady-state plasma load of ∼1 MW/m2 led to erosion, cracking, and nanostructured “fuzz” structure growth on the material surface. The capillary porous system of liquid tin was tested with steady-state plasma in PLM during ∼200 min demonstrating sustainability under high heat plasma load. Lithium materials deposited in the T-10 tokamak during experiments with lithium capillary-porous system have been irradiated with stationary steady-state plasma in PLM to test the evolution of the deposits under long-term plasma load.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2020.111694