(НИЯУ МИФИ, 2015) OGORODNIKOVA, O. V.; GANN, V.; ZIBROV, M.; GASPARYAN, Yu.; EFIMOV, V.; Ефимов, Виталий Сергеевич; Гаспарян, Юрий Микаэлович; Огородникова, Ольга Вячеславовна
Due to high melting temperature, low erosion yield and low retention of hydrogen isotopes, tungsten (W) is used as plasma-facing materials in present tokamaks as ASDEX Upgrade (AUG) [1] and JET [2] and selected to be used in future fusion devices as material facing to the plasma [3,4]. In previous works it was shown that pre-irradiation with self-ions [5-8] and with neutrons at high-flux isotope reactor (HFIR) [9,10] significantly increases the deuterium (D) retention in W. In the present work, we investigate the D retention in W in dependence on the pre-irradiation with different species. The objective of this work is to compare the deuterium retention in tungsten pre-damaged with electrons (e), ions and neutrons. Self-ion irradiation was performed at IPP (Garching) with 20 MeV W ions, e-beam irradiation at MEPhI (Moscow) with 3.5 MeV e-, and neutron irradiation at Oak Ridge National Laboratory in highflux isotope reactor (HFIR) [10]. After pre-damaging, specimens were exposed to deuterium plasma in well-defined laboratory conditions.