Study of ion-irradiated tungsten in deuterium plasma

• Published in: Journal of nuclear materials Vol. 438; pp. 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: Journal Article
• Language: English
• Published: Elsevier B.V 01-07-2013
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2013.01.221

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.