Study of ion-irradiated tungsten in deuterium plasma

Experimental study aimed at investigation of neutron induced damage influence on fusion reactor plasma facing materials is reported. Displacement damage was produced in tungsten by high-energy helium and carbon ions at 3–10MeV. The reached level of displacement damage ranged from several dpa to 600d...

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Bibliographic Details
Published in:Journal of nuclear materials 2013-07, Vol.438, p.S1014-S1018
Main Authors: Khripunov, B.I., Gureev, V.M., Koidan, V.S., Kornienko, S.N., Latushkin, S.T., Petrov, V.B., Ryazanov, A.I., Semenov, E.V., Stolyarova, V.G., Danelyan, L.S., Kulikauskas, V.S., Zatekin, V.V., Unezhev, V.N.
Format: Article
Language:English
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Summary:Experimental study aimed at investigation of neutron induced damage influence on fusion reactor plasma facing materials is reported. Displacement damage was produced in tungsten by high-energy helium and carbon ions at 3–10MeV. The reached level of displacement damage ranged from several dpa to 600dpa. The properties of the irradiated tungsten were studied in steady-state deuterium plasma on the LENTA linear divertor simulator. Plasma exposures were made at 250eV of ion energy to fluence 1021–1022ion/сm2. Erosion dynamics of the damaged layer and deuterium retention were observed. Surface microstructure modifications and important damage of the 5μm layer shown. Deuterium retention in helium-damaged tungsten (ERD) showed its complex behavior (increase or decrease) depending on implanted helium quantity and the structure of the surface layer.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2013.01.221