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Global Nuclear Fuel - Japan Co, Ltd. (Japan)

Homepage: gnfjapan.com
Alternate names: Global Nuclear Fuel - Japan, Global Nuclear Fuel - Japan Co, Ltd., 株式会社グローバル・ニュークリア・フュエル・ジャパン
ROR: 04g1c6t06
OpenAlex ID: I4405275897
Dissolution and precipitation behavior of hydrides in Zircaloy-2 and high Fe Zircaloy
2003 · K. Une, S. Ishimoto · Journal of Nuclear Materials · 128
Benchmark Problem Suite for Reactor Physics Study of LWR Next Generation Fuels
2002 · Akio YAMAMOTO, Tadashi IKEHARA, et al. · Journal of Nuclear Science and Technology · 113
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Crystallography of Zirconium Hydrides in Recrystallized Zircaloy-2 Fuel Cladding by Electron Backscatter Diffraction
2004 · Katsumi UNE, Kazuhiro NOGITA, et al. · Journal of Nuclear Science and Technology · 110
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Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan
2021 · K. Sakamoto, Y. Miura, et al. · Journal of Nuclear Materials · 87
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Terminal Solid Solubility of Hydrogen in Unalloyed Zirconium by Differential Scanning Calorimetry
2004 · Katsumi UNE, Shinji ISHIMOTO · Journal of Nuclear Science and Technology · 70
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A metallographic and fractographic study of outside-in cracking caused by power ramp tests
2004 · S. Shimada, E. Etoh, et al. · Journal of Nuclear Materials · 68
The terminal solid solubility of hydrogen in irradiated Zircaloy-2 and microscopic modeling of hydride behavior
2009 · K. Une, S. Ishimoto, et al. · Journal of Nuclear Materials · 67
Two-phase Flow Patterns in a Four by Four Rod Bundle
2007 · Yoshitaka MIZUTANI, Akio TOMIYAMA, et al. · Journal of Nuclear Science and Technology · 62
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Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation-Induced Growth Behavior of Zirconium Alloy Variants
2018 · Suresh Yagnik, Ronald Adamson, et al. · 42
Fission Gas Release Behavior from High Burnup UO 2 Fuels under Rapid Heating Conditions
2006 · Katsumi UNE, Shinji KASHIBE, et al. · Journal of Nuclear Science and Technology · 41
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Stress Reorientation of Hydrides in Recrystallized Zircaloy-2 Sheet
2006 · Kan SAKAMOTO, Masafumi NAKATSUKA · Journal of Nuclear Science and Technology · 39
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Effect of Gd2O3 Dispersion on the Thermal Conductivity of UO2
2009 · Kouta IWASAKI, Tsuneo MATSUI, et al. · Journal of Nuclear Science and Technology · 37
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Hydrogen Absorption Mechanism of Zirconium Alloys Based on Characterization of Oxide Layer
2011 · K. Une, K. Sakamoto, et al. · Journal of ASTM International · 25
Development of nuclear data processing code FRENDY version 2
2023 · Kenichi Tada, Akio Yamamoto, et al. · Journal of Nuclear Science and Technology · 22
The Correlation Between Microstructures and in-BWR Corrosion Behavior of Highly Irradiated Zr-based Alloys
2005 · Y Takagawa, S Ishimoto, et al. · 22
Heat Capacity Measurements of U1-yGdyO2 (y=0-0.27) from 325 to 1,673K
2004 · Masaki AMAYA, Katsumi UNE, et al. · Journal of Nuclear Science and Technology · 20
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Development of Kinetics Model for BWR Core Simulator AETNA
2003 · Masashi TAMITANI, Tatsuya IWAMOTO, et al. · Journal of Nuclear Science and Technology · 20
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Current Status of the Post Boiling Transition Research in Japan
2003 · Takashi HARA, Shinya MIZOKAMI, et al. · Journal of Nuclear Science and Technology · 18
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Fission Gas Release Behavior in High Burnup UO2 Fuels with Developed Rim Structure
2002 · Katsumi Une, Shinji Kashibe, et al. · Journal of Nuclear Science and Technology · 17
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Change of chemical states of niobium in the oxide layer of zirconium–niobium alloys with oxide growth
2015 · Kan Sakamoto, Katsumi Une, et al. · Journal of Nuclear Science and Technology · 16
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Effect of proton irradiation on deuterium diffusion in zirconium oxide layer
2011 · K. Une, I. Takagi, et al. · Journal of Nuclear Materials · 12
Effect of Subchannel Void Fraction Distribution on Lattice Physics Parameters for Boiling Water Reactor Fuel Bundles
2008 · Tadashi IKEHARA, Yoshiro KUDO, et al. · Journal of Nuclear Science and Technology · 12
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BWR Stability Issues in Japan
2007 · Hideaki Ikeda, Takanori Fukahori, et al. · Science and Technology of Nuclear Installations · 12
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The Correlation Between Microstructures and in-BWR Corrosion Behavior of Highly Irradiated Zr-based Alloys
2005 · Y Takagawa, S Ishimoto, et al. · Journal of ASTM International · 12
Depth profile of chemical states of alloying elements in oxide layer of Zr-based alloys
2012 · K. Sakamoto, K. Une, et al. · Progress in Nuclear Energy · 11
Works count: 133
Citation count: 2,174
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