@article{oai:repo.qst.go.jp:00077683,
 author = {Chikada, Takumi and Kimura, Keisuke and Mochizuki, Jumpei and Horikoshi, Seira and Matsunaga, Moeki and Fujita, Hikari and Okitsu, Kouhei and Tanaka, Teruya and Hishinuma, Yoshimitsu and Sakamoto, Yoshiteru and Someya, Youji and Nakamura, Hirofumi and Yoshiteru, Sakamoto and Yoji, Someya and Hirofumi, Nakamura},
 issue = {A},
 journal = {Fusion Engineering and Design},
 month = {Sep},
 note = {Fuel loss and environmental contamination by tritium permeation through structural materials are critical issuesfor the establishment of a fusion DEMO reactor. In this study, the effectivity of a chromium oxide layer formedon reduced activation ferritic/martensitic steel F82H as a tritium permeation barrier and its stability undersimulated solid/liquid breeder blanket conditions have been investigated. A uniform 100-nm-thick chromiumoxide layer was formed by heat treatment at 710 °C for 5 min in 50% argon-50% hydrogen mixed gas with theflow rate of 200 standard cubic centimeter per minute. After exposure to simulated solid breeder blanket con-ditions, an iron oxide layer and a spinel-type iron-chromium oxide layer formed. In the case of a liquid breederblanket condition, the chromium oxide layer partly lost at 500 °C for 100 h. The chromium oxide-formed sampledecreased deuterium permeationflux by a factor of up to 150. The permeation reduction efficiency deterioratedafter exposure to a solid breeder blanket condition due to a change of the chromium oxide layer. However, thechromium oxide formation would play a role to reduce hydrogen isotope permeation even after reduction of theoxide layers},
 pages = {450--454},
 title = {Surface oxidation effect on deuterium permeation in reduced activation ferritic/martensitic steel F82H for DEMO application},
 volume = {146},
 year = {2019}
}