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Suzudo, Tomoaki; Tsuru, Tomohito; Hasegawa, Akira*
Journal of Nuclear Materials, 505, p.15 - 21, 2018/07
Times Cited Count：17 Percentile：86.67(Materials Science, Multidisciplinary)Tungsten (W) is considered as a promising candidate for plasma-facing materials for future nuclear fusion devices, and selecting optimal alloying constituents is a critical issue to improve radiation resistance of the W alloys as well as to improve their mechanical properties. We conducted in the current study a series of first-principles calculations for investigating solvent-solute mixed dumbbells in W crystals. The results suggested that titanium (Ti), vanadium (V), and chromium (Cr) are favorable as solutes for W alloys from irradiation-effect perspectives because these elements are expected to promote vacancy-interstitial recombination without causing radiation-induced precipitation that reduces ductility of irradiated materials.
Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Tsuji, Hirokazu; Nakajima, Hajime
Journal of Nuclear Science and Technology, 37(11), p.949 - 958, 2000/11
no abstracts in English
Kaji, Yoshiyuki; Tsukada, Takashi; Miwa, Yukio; Tsuji, Hirokazu; Nakajima, Hajime
Environmentally Assisted Crarking (ASTM STP 1401), p.191 - 209, 2000/00
no abstracts in English
Kaji, Yoshiyuki; Tsukada, Takashi; Tsuji, Hirokazu; Nakajima, Hajime
Proceedings of 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, p.987 - 995, 1999/00
no abstracts in English
Morinaga, Masahiko*; Inoue, Satoshi*; Saito, Junichi*; *; *; Kano, Shigeki; Tachi, Yoshiaki
PNC TY9623 93-005, 134 Pages, 1993/03
None
Suzudo, Tomoaki; Tsuru, Tomohito; Hasegawa, Akira*
no journal, ,
Tungsten is a promising candidate for plasma-facing materials for the first wall and the divertor of future fusion reactors due to its high melting point, high sputtering resistance and low hydrogen retention. However, under irradiation, several problems have been pointed out. First, ruthenium and osmium produced by nuclear transformation form irradiated induced precipitation, and the ductility of the material is decreased. In addition, irradiation defects in tungsten serve as trapping sites for hydrogen isotopes, increasing the retention amount. However, it has also been pointed out experimentally that residual irradiation defects decrease due to the presence of rhenium, and the retention problem may be alleviated. In this presentation, we analyze the interaction of rhenium and osmium with irradiation defects by using computational method and irradiation experiment result, and we discuss the elements to be added for irradiation resistant tungsten materials.
