Erosion and deuterium retention in ion-irradiated tungsten under plasma exposureстатья
Статья опубликована в высокорейтинговом журнале
Информация о цитировании статьи получена из
Web of Science,
Scopus
Статья опубликована в журнале из списка Web of Science и/или Scopus
Дата последнего поиска статьи во внешних источниках: 13 ноября 2015 г.
Авторы:
Khripunov B.,
Gureev V.,
Koidan V.,
Kornienko S.,
Latushkin S.,
Petrov V.,
Ryazanov A.,
Semenov E.,
Stolyarova V.,
Danelyan L.,
Kulikauskas V.,
Zatekin V.,
Unezhev V.
Аннотация:Effect of radiation damage on tungsten response to plasma exposure is examined. Samples of tungstenW
99.95 wt% were irradiated with fast 12C3+ ions at 10 MeV to fluence of (1–2) 1017 ion/cm2 to produce
damage in the range 1–40 dpa relevant to the level of interest for fusion research. Exposure of the
irradiated tungsten to deuterium plasma on linear simulator in erosion condition provided D-ion total
fluence (1–3) 1021 D+/cm2 at ion energy 250 eV. Swelling effect has been observed, and important
changes in the structure of the irradiated material have been found (SEM). Erosion of the damaged layer
was evaluated at Yd-w ffi (3–5) 103 at/ion. The retained deuterium profiles have been taken by ERDA,
maximal deuterium concentration reached 6–8 at.% in the layer 30 nm deep corresponding to 2–
3 dpa. Comparison of D-retention was made for C- and He-irradiated tungsten for this level of damage.