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Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD
Nuclear Materials and Energy
In the present study, an additional deuterium (D) ion irradiation was performed against long-term samples mounted on the helical coil can and in the outer private region in the LHD during the 17th experimental campaign. Based on the release behavior of the D and hydrogen (H) retained during the experimental campaign, the difference of release behavior at the top surface and in bulk of modified surfaces is discussed. Almost all samples on the helical coil can were erosion-dominant and somedoi:10.1016/j.nme.2017.02.025 fatcat:dirysgpyfre5jf7mut2ofvjuum