Hirotaka Furuya - Concepedia

Author

Hirotaka Furuya

Kyushu University

Also Known As

H Furuya, H. FURUYA, H. Furuya, Hirotaka FURUYA, Hirotaka Furuya

157

Publications

1.2K

Citations

H-Index

Concepts

All Affiliations

Kyushu University Japan Atomic Energy Agency

About

Hirotaka Furuya is an author at Kyushu University specializing in engineering, materials science, and chemical engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	18	38	751
2	Chemical Engineering	14	19	393
3	Applied Physics	7	7	153
4	Natural Sciences	2	2	42
5	Health Sciences	1	1	14

Hirotaka Furuya

Publications

863

Citations

H-Index

Page 1

	Year	Citations
Oxidation kinetics of Zircaloy-2 between 450°C and 600°C in oxidizing atmosphere T. Arima, Kouki Moriyama, N. Gaja, Journal of Nuclear Materials Advanced Oxidation ProcessChemical EngineeringOxidation KineticsEngineeringCorrosion	1998	42
Microstructure of Simulated High-Level Waste Glass Doped with Short-Lived Actinides, <sup>238</sup>Pu and <sup>244</sup>Cm Yuji Inagaki, Hirotaka Furuya, Kazuya Idemitsu, MRS Proceedings Materials ScienceGlass-ceramicEngineeringApplied PhysicsGlass Material	1991	38
Distributions of volatile fission products in or near the fuel-cladding gap of the FBR MOX fuel pins irradiated to high burn-up Koji Maeda, Kosuke Tanaka, Takeo Asaga, Journal of Nuclear Materials Materials ScienceNuclear CeramicChemical EngineeringNuclear Fuel BurnupEngineering	2005	36
Basic Study on an Antenna Made of a Transparent Conductive Film Ning Guan, Hirotaka Furuya, K. Himeno, IEICE Transactions on Communications Electrical EngineeringEngineeringAntenna TestingAntenna MadeTransparent Conductive Film	2007	34
Behavior of metallic fission products in uranium–plutonium mixed oxide fuel Isamu Sato, Hirotaka Furuya, T. Arima, Journal of Nuclear Materials Materials ScienceFuel CycleChemical EngineeringNuclear CeramicNuclear Fuel Burnup	1999	32
Behavior of Fission Products Zirconium and Barium in Fast Reactor Fuel Irradiated to High Burnup Isamu Sato, Hirotaka Furuya, Tatsumi Arima, Journal of Nuclear Science and Technology	1999	32
Corrosion behavior of a powdered simulated nuclear waste glass: A corrosion model including diffusion process Yuji Inagaki, Hirotaka Furuya, Kazuya Idemitsu, Journal of Nuclear Materials Materials ScienceGlass-ceramicChemical EngineeringNuclear Waste ManagementEngineering	1994	32
Volumetric change of simulated radioactive waste glasses irradiated by the B(n, α)Li Reaction as simulation of actinide irradiation Seichi Sato, Hirotaka Furuya, Tetsuo Kozaka, Journal of Nuclear Materials Materials ScienceVolumetric ChangeNuclear Waste ManagementEngineeringApplied Physics	1988	31
Radiation effect of simulated waste glass irradiated with ion, electron and γ-ray Seichi Sato, Hirotaka Furuya, Koichi Asakura, Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms EngineeringRadiation Materials ScienceRadiation PhysicsIonizing RadiationSimulated Waste Glass	1984	28
Dependence on Strain Rate and Temperature Shown by Yield Stress of Uranium Dioxide Toshimichi Tachibana, Hirotaka Furuya, Masumichi Koizumi Journal of Nuclear Science and Technology Materials ScienceYield StrengthPolycrystalline Uo2EngineeringMechanical Properties	1976	28

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