User profiles for "author:Akihiko Kimura"
Akihiko KimuraKyoto University Verified email at iae.kyoto-u.ac.jp Cited by 74294 |
Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications
Significant progress has been achieved in the international research effort on reduced
activation ferritic/martensitic steels for fusion structural applications. Because this class of …
activation ferritic/martensitic steels for fusion structural applications. Because this class of …
Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges
M Mayer, S Möller, M Rubel, A Widdowson… - Nuclear …, 2019 - iopscience.iop.org
Abstract Following the IAEA Technical Meeting on'Advanced Methodologies for the Analysis
of Materials in Energy Applications Using Ion Beam Accelerators', this paper reviews the …
of Materials in Energy Applications Using Ion Beam Accelerators', this paper reviews the …
Recent progress in US–Japan collaborative research on ferritic steels R&D
The mechanisms of irradiation embrittlement of two Japanese RAFSs were different from
each other. The larger DBTT shift observed in F82H is interpreted by means of both …
each other. The larger DBTT shift observed in F82H is interpreted by means of both …
Formation mechanism and the role of nanoparticles in Fe-Cr ODS steels developed for radiation tolerance
LL Hsiung, MJ Fluss, SJ Tumey, BW Choi, Y Serruys… - Physical Review B, 2010 - APS
Structures of nanoparticles in Fe-16 Cr-4.5 Al-0.3 Ti-2 W-0.37 Y 2 O 3 (K3) and Fe-20 Cr-4.5
Al-0.34 Ti-0.5 Y 2 O 3 (MA956) oxide dispersion strengthened (ODS) ferritic steels produced …
Al-0.34 Ti-0.5 Y 2 O 3 (MA956) oxide dispersion strengthened (ODS) ferritic steels produced …
A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques
R Kasada, Y Takayama, K Yabuuchi… - Fusion engineering and …, 2011 - Elsevier
The present work investigates the irradiation hardening of Fe-based model ferritic alloys
after Fe-ion irradiation experiments in order to deduce mechanistically based nominal …
after Fe-ion irradiation experiments in order to deduce mechanistically based nominal …
Absence of IL-1 receptor antagonist impaired wound healing along with aberrant NF-κB activation and a reciprocal suppression of TGF-β signal pathway
Although enhanced expression of IL-1 family proteins, including IL-1α, IL-1β, and IL-1
receptor antagonist (IL-1ra) during wound healing has been observed, the …
receptor antagonist (IL-1ra) during wound healing has been observed, the …
Mutations in the Canalicular Multispecific Organic Anion Transporter (cMOAT) Gene, a Novel ABC Transporter, in Patients with Hyperbilirubinemia II/Dubin-Johnson …
M Wada, S Toh, K Taniguchi… - Human molecular …, 1998 - academic.oup.com
Members of the ATP-binding cassette (ABC) transporter superfamily are mutated to cause
diseases that include cystic fibrosis, hyperinsulinemia, adrenoleukodys-trophy, Stargardt …
diseases that include cystic fibrosis, hyperinsulinemia, adrenoleukodys-trophy, Stargardt …
Production of thick high-performance sintered neodymium magnets by grain boundary diffusion treatment with dysprosium–nickel–aluminum alloy
A novel grain boundary diffusion (GBD) treatment with a Dy–Ni–Al eutectic alloy powder
allowed Dy to penetrate into sintered plates of Nd–Fe–B magnet as thick as 5mm. The …
allowed Dy to penetrate into sintered plates of Nd–Fe–B magnet as thick as 5mm. The …
TEM and HRTEM study of oxide particles in an Al-alloyed high-Cr oxide dispersion strengthened steel with Zr addition
The nanoparticles in an Al-alloyed high-Cr oxide dispersion strengthened (ODS) steel with
Zr addition, ie, SOC-14 (Fe–15Cr–2W–0.1 Ti–4Al–0.63 Zr–0.35 Y 2 O 3), have been …
Zr addition, ie, SOC-14 (Fe–15Cr–2W–0.1 Ti–4Al–0.63 Zr–0.35 Y 2 O 3), have been …
Status of R&D activities on materials for fusion power reactors
N Baluc, K Abe, JL Boutard, VM Chernov… - Nuclear …, 2007 - iopscience.iop.org
Current R&D activities on materials for fusion power reactors are mainly focused on plasma
facing, structural and tritium breeding materials for plasma facing (first wall, divertor) and …
facing, structural and tritium breeding materials for plasma facing (first wall, divertor) and …