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Nanoindentation hardness and its extrapolation to bulk-equivalent hardness of F82H steels after single- and dual-ion beam irradiation

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.S23-S27

2013

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Positron annihilation study on the phase transition of thermally aged Fe-Cr binary alloys at 748K

Philosophical magazine letters, 2019-10, Vol.99 (10), p.360-371

2019

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Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.176-179

2011

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Corrosion behaviour of 16%Cr–4%Al and 16%Cr ODS ferritic steels under different metallurgical conditions in a supercritical water environment

Corrosion science, 2010-10, Vol.52 (10), p.3266-3270

2010

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Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation

Journal of nuclear materials, 2007-08, Vol.367, p.423-427

2007

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Stability of Y–Ti complex oxides in Fe–16Cr–0.1Ti ODS ferritic steel before and after heavy-ion irradiation

Journal of nuclear materials, 2009-04, Vol.386, p.533-536

2009

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Fuel flow and stock during deuterium-deuterium start-up of fusion reactor with advanced plasma model

Fusion engineering and design, 2020-11, Vol.160, p.111794, Article 111794

2020

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Recrystallization of cold rolled oxide dispersion strengthened copper during room temperature annealing

Journal of alloys and compounds, 2019-08, Vol.798, p.187-193

2019

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Brass-texture induced grain structure evolution in room temperature rolled ODS copper

Materials science & engineering. A, Structural materials : properties, microstructure and processing, 2019-03, Vol.749, p.118-128

2019

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Influence of alloy composition and temperature on corrosion behavior of ODS ferritic steels

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.1225-1228

2011

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Microstructure development and high tensile properties of He/H2 milled oxide dispersion strengthened copper

Journal of alloys and compounds, 2019-04, Vol.783, p.674-679

2019

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Chemical State Mapping of Degraded B4C Control Rod Investigated with Soft X-ray Emission Spectrometer in Electron Probe Micro-analysis

Scientific reports, 2016-05, Vol.6 (1), p.25700-25700, Article 25700

2016

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Microstructure and mechanical properties of mechanically alloyed ODS copper alloy for fusion material application

Nuclear materials and energy, 2018-05, Vol.15, p.17-22

2018

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Pre- and post-deformation microstructures of oxide dispersion strengthened ferritic steels

Journal of nuclear materials, 2007-08, Vol.367, p.222-228

2007

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Effects of tensile stress on Cu clustering in irradiated Fe–Cu alloy

Journal of nuclear materials, 2015-03, Vol.458, p.281-287

2015

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Anisotropy in tensile and ductile–brittle transition behavior of ODS ferritic steels

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.180-184

2011

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Characterization of the oxide particles in Al-added high-Cr ODS ferritic steels

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.221-224

2011

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Longitudinal and shear wave velocities in pure tungsten and tungsten fiber-reinforced tungsten composites

Physica scripta, 2017-12, Vol.T170 (1), p.14024

2017

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Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

Fusion engineering and design, 2008-12, Vol.83 (10), p.1471-1476

2008

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In-situ fabrication of yttria dispersed copper alloys through MA-HIP process

Nuclear materials and energy, 2018-08, Vol.16, p.168-174

2018

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Small specimen test technology and methodology of IFMIF/EVEDA and the further subjects

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.1325-1330

2011

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Heavy-ion irradiation effects on the morphology of complex oxide particles in oxide dispersion strengthened ferritic steels

Journal of nuclear materials, 2007-08, Vol.367, p.179-184

2007

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Recent progress of tungsten R&D for fusion application in Japan

Physica scripta, 2011-12, Vol.2011, p.014029

2011

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Ion-Irradiation Hardening of Brazed Joints of Tungsten and Oxide Dispersion Strengthened (ODS) Ferritic Steel

Materials transactions, 2013-01, Vol.54 (4), p.446-450

2013

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Effects of stress on radiation hardening and microstructural evolution in A533B steel

Journal of nuclear materials, 2010-12, Vol.407 (3), p.151-156

2010

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Nanoindentation hardness and its extrapolation to bulk-equivalent hardness of F82H steels after single- and dual-ion beam irradiation

Positron annihilation study on the phase transition of thermally aged Fe-Cr binary alloys at 748K

Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems

Corrosion behaviour of 16%Cr–4%Al and 16%Cr ODS ferritic steels under different metallurgical conditions in a supercritical water environment

Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation

Stability of Y–Ti complex oxides in Fe–16Cr–0.1Ti ODS ferritic steel before and after heavy-ion irradiation

Fuel flow and stock during deuterium-deuterium start-up of fusion reactor with advanced plasma model

Recrystallization of cold rolled oxide dispersion strengthened copper during room temperature annealing

Brass-texture induced grain structure evolution in room temperature rolled ODS copper

Influence of alloy composition and temperature on corrosion behavior of ODS ferritic steels

Microstructure development and high tensile properties of He/H2 milled oxide dispersion strengthened copper

Chemical State Mapping of Degraded B4C Control Rod Investigated with Soft X-ray Emission Spectrometer in Electron Probe Micro-analysis

Microstructure and mechanical properties of mechanically alloyed ODS copper alloy for fusion material application

Pre- and post-deformation microstructures of oxide dispersion strengthened ferritic steels

Effects of tensile stress on Cu clustering in irradiated Fe–Cu alloy

Anisotropy in tensile and ductile–brittle transition behavior of ODS ferritic steels

Characterization of the oxide particles in Al-added high-Cr ODS ferritic steels

Longitudinal and shear wave velocities in pure tungsten and tungsten fiber-reinforced tungsten composites

Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

In-situ fabrication of yttria dispersed copper alloys through MA-HIP process

Small specimen test technology and methodology of IFMIF/EVEDA and the further subjects

Heavy-ion irradiation effects on the morphology of complex oxide particles in oxide dispersion strengthened ferritic steels

Recent progress of tungsten R&D for fusion application in Japan

Ion-Irradiation Hardening of Brazed Joints of Tungsten and Oxide Dispersion Strengthened (ODS) Ferritic Steel

Effects of stress on radiation hardening and microstructural evolution in A533B steel

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