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Naoyuki Hashimoto

Researcher at Hokkaido University

Publications -  182
Citations -  4213

Naoyuki Hashimoto is an academic researcher from Hokkaido University. The author has contributed to research in topics: Irradiation & Hardening (metallurgy). The author has an hindex of 30, co-authored 172 publications receiving 3587 citations. Previous affiliations of Naoyuki Hashimoto include Hiroshima University & Oak Ridge National Laboratory.

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The swelling, microstructure, and hardening of wrought LCAC, TZM, and ODS molybdenum following neutron irradiation

TL;DR: TEM examinations and swelling measurements were performed on commercially available wrought Low Carbon Arc Cast (LCAC), La-oxide Oxide Dispersion Strengthened (ODS), and TZM molybdenum alloys following irradiation in the High Flux Isotope Reactor (HFIR) at 300, 600, and 900,°C to neutron fluences between 1.05 and 24.1 dpa as discussed by the authors.
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Effects of hydrogen on activation volume and density of mobile dislocations in iron-based alloy

TL;DR: In this paper, the authors evaluate the hydrogen effect on coupled evolution of dislocation velocity and mobile dislocation density in Fe-based alloys, thermal activation parameters and dislocation structures were obtained using repeated stress relaxation tests on pure iron, Fe-8Cr alloy and F82H steel.
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Low temperature neutron irradiation effects on microstructure and tensile properties of molybdenum

TL;DR: In this paper, the deformation microstructure of polycrystalline molybdenum was characterized by room-temperature electrical resistivity measurements, transmission electron microscopy (TEM) and positron annihilation spectroscopy (PAS).
Journal Article

Strain localization in irradiated materials

TL;DR: In this paper, a review on the radiation effects on the deformation of metallic materials, focusing on microscopic and macroscopic strain localization phenomena was provided, and it was shown that the plastic instability stress and true fracture stress are nearly independent of irradiation dose if there is no radiation-induced phase change or embrittlement.
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Micro-structure and micro-hardness of ODS steels after ion irradiation

TL;DR: The radiation-hardening of oxide dispersion strengthened (ODS) alloys was examined using ion irradiation and nano-indentation in this article, where three ODS steels were irradiated in the TIARA facility at JAEA with 10.5 MeV Fe 3+ ions up to a dose of 20dpa at 250 and 380°C.