M
Makoto Oya
Researcher at Kyushu University
Publications - 25
Citations - 139
Makoto Oya is an academic researcher from Kyushu University. The author has contributed to research in topics: Irradiation & Tungsten. The author has an hindex of 6, co-authored 25 publications receiving 95 citations. Previous affiliations of Makoto Oya include University of Toyama & Osaka University.
Papers
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Journal ArticleDOI
Deuterium retention in Toughened, Fine-Grained Recrystallized Tungsten
Makoto Oya,K. Uekita,Heun Tae Lee,Y. Ohtsuka,Yoshio Ueda,Hiroaki Kurishita,Arkadi Kreter,J. W. Coenen,V. Philipps,S. Brezinsek,Andrey Litnovsky,K. Sugiyama,Yuji Torikai +12 more
TL;DR: In this paper, the deuterium retention in TFGR W (TFGR W-1.1%TiC) was studied, compared to pure W. D implantation was performed to a fluence of 1.5×1024m−2 at temperatures of 473-873k, followed by TDS.
Journal ArticleDOI
Deuterium retention in various toughened, fine-grained recrystallized tungsten materials under different irradiation conditions
Makoto Oya,Heun Tae Lee,Y. Ohtsuka,Yoshio Ueda,Hiroaki Kurishita,M Oyaidzu,Toshihiko Yamanishi +6 more
TL;DR: In this paper, the deuterium retention in two types of toughened, fine-grained recrystallized W (TFGR W-1.2 wt% titanium carbide (TiC) and TFGRW W-3.3wt% tantalum carbide(TaC)) was studied, compared to pure W. This may be due to different types of dispersoids.
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Influence of helium on deuterium retention in reduced activation ferritic martensitic steel (F82H) under simultaneous deuterium and helium irradiation
TL;DR: In this paper, tritium retention behavior in RAFM steels was investigated under simultaneous D-He irradiation at 500, 625, 750, and 818 K and the irradiation fluence was kept constant at 1 × 1024 D m−2.
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Surface erosion and modification of toughened, fine-grained, recrystallized tungsten exposed to TEXTOR edge plasma
Yoshio Ueda,Makoto Oya,Y. Hamaji,Heun Tae Lee,Hiroaki Kurishita,Yuji Torikai,Nobuaki Yoshida,Arkadi Kreter,J. W. Coenen,Andrey Litnovsky,V. Philipps +10 more
TL;DR: In this paper, the applicability of toughened, fine-grained, recrystallized (TFGR)-W to the tokamak edge plasma environment was evaluated.
Journal ArticleDOI
Surface morphology changes and deuterium retention in Toughened, Fine-grained Recrystallized Tungsten under high-flux irradiation conditions
Makoto Oya,Heun Tae Lee,Yoshio Ueda,Hiroaki Kurishita,M. Oyaidzu,Takumi Hayashi,Nobuaki Yoshida,Thomas Morgan,G. De Temmerman +8 more
TL;DR: In this article, surface morphology changes and deuterium retention in Toughened, Fine-Grained Recrystallized Tungsten (TFGR W) with TaC dispersoids (W-TaC) and pure tungsten exposed to D plasmas to a fluence of 1026-D/m2