Get started
Author

Hideki Yuya

Observed names: H Yuya, H. Yuya, Hideki YUYA, Yuya Hideki
ORCID: 0000-0003-2290-1240
Observed ORCID: 0000-0003-2290-1240
OpenAlex ID: A5001137719
Investigation of electromagnetic nondestructive evaluation of residual strain in low carbon steels using the eddy current magnetic signature (EC-MS) method
2019 · Takanori Matsumoto, Tetsuya Uchimoto, et al. · Journal of Magnetism and Magnetic Materials · 62
Microstructure and pitting behavior of the dissimilar metal weld of 309L cladding and low alloy steel A533B
2018 · Zihao Wang, Jian Xu, et al. · Journal of Nuclear Materials · 32
Radiation embrittlement of clad-HAZ of RPV of a decommissioned BWR plant
2021 · Hideki Yuya, Kiyohiro Yabuuchi, et al. · Journal of Nuclear Materials · 19
Investigation of measurement conditions of eddy current magnetic signature method for evaluating plastic deformation in carbon steels
2018 · Takanori Matsumoto, Tetsuya Uchimoto, et al. · International Journal of Applied Electromagnetics and Mechanics · 12
Cross-sectional TEM and X-ray examination of radiation-induced stress relaxation of peened stainless steel surfaces
2004 · B.H. Sencer, G.S. Was, et al. · Journal of Nuclear Materials · 12
Microstructure and mechanical properties of HAZ of RPVS clad with duplex stainless steel
2020 · Hideki Yuya, Ryoya Kobayashi, et al. · Journal of Nuclear Materials · 10
First-principles calculations of hydrogen interactions with nickel containing a monovacancy and divacancies
2017 · Nishith K Das, Tetsuo Shoji, et al. · Materials Research Express · 9
Effects of Proton Irradiation on Positron Annihilation and Micro-Vickers Hardness of Fe-C-Cu Model Alloys
1996 · H Shibamoto, K Koyama, et al. · 9
Damage Structures of Proton Irradiated Fe-0.3wt.%Cu Alloy
1996 · A Kimura, H Shibamoto, et al. · 7
In situ weak-beam scanning transmission electron microscopy observation of geometrically necessary dislocations formed by Mn precipitates in A533B alloy steel
2024 · Kenta Yoshida, Hotaka Miyata, et al. · Materialia · 3
Evaluating the irradiation hardening of reactor pressure vessel steels by nanoindentation hardness test and micropillar compression test
2022 · Yuyang Zheng, Diancheng Geng, et al. · Journal of Nuclear Science and Technology · 3
Proposal of SCC Crack Growth Rate Curve for Nickel-Base Alloy Weld Metal in BWR Environments(<Special Issue>M & M 2009 Conference)
2010 · Hiroshi NAGASE, Haruo FUJIMORI, et al. · TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A · 3
PDF
Interaction and diffusion of atomic oxygen in monovacancy-containing Cr- and Ti-doped nickel structures
2019 · Nishith Kumar Das, Tetsuo Shoji, et al. · Physica B Condensed Matter · 2
Current understanding on the neutron irradiation embrittlement of BWR reactor pressure vessel steels in Japan
2011 · K. Asano, Takio Nishiyama, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
Formulation of the Stress Corrosion Crack Growth Rates for the Practical Use in the Integrity Assessment of Nuclear Reactor Components
2018 · Masato Koshiishi, Satoru Aoike, et al. · ASME Pressure Vessels and Piping Conference (PVP) · 1
Application of Stress Intensity Factors for Deep Surface Cracks to Crack Growth Evaluation
2013 · Fuminori Iwamatsu, Katsumasa Miyazaki, et al. · ASME Pressure Vessels and Piping Conference (PVP) · 1
Detection and Depth Sizing of Corrosion Defects in Anchor Bolts
2012 · Hideki Yuya, Shan Lin, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
Feasibility Study on a Simple Method of Retrospective Neutron Dosimetry for Reactor Internals and Reactor Vessel
2006 · K Hayashi, R Tayama, et al. · Journal of ASTM International · 1
Diffuse X-ray scattering studies of radiation defects in Ni and dilute Ni alloys
1999 · Hideki Yuya, Hiroshi Maeta, et al. · Journal of Nuclear Materials · 1
Defect clusters in high-energy ion-irradiated Ni and dilute Ni alloys investigated by diffuse X-ray scattering
1999 · Hideki Yuya, Tsuneo Matsui, et al. · Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms · 1
The effect of negative dK/dt on crack growth behavior of Alloy 182, Alloy 82 and low alloy steel in a simulated BWR water environment
2026 · Yunlong Wu, Xiangyu Zhong, et al. · Corrosion Science
Investigation of SCC behavior in 309 SS clad DMWs under seawater ingress using novel high-temperature autoclave
2026 · Yunlong Wu, Katsumi Ito, et al. · Corrosion Communications
IHSI Effectiveness for Crack Propagation Observed at Hamaoka PLR Piping
2020 · Hideki Yuya, Kouji Yamada, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
A Research of the Japanese Decommisioning Reactor Materials (Charpy Impact Test)
2020 · Hideki Yuya · Atomic Energy Society of Japan
Study on corrosion immunity of RPV inner welding
2017 · Hideki Yuya · Atomic Energy Society of Japan
Works count: 37
Citation count: 191
H-index: 8
I10-index: 6
Year
Topic
Type