Nippon Nuclear Fuel Development (Japan)

Homepage: nfd.jp

Alternate name: 日本核燃料開発

Related institutions: Toshiba (Japan), Hitachi (Japan)

ROR: 057a94j04

OpenAlex ID: I4405285325

Formation and growth of intragranular fission gas bubbles in UO2 fuels with burnup of 6–83 GWd/t

1993 · S. Kashibe, K. Une, et al. · Journal of Nuclear Materials · 181

Irradiation-induced recrystallization in high burnup UO2 fuel

1995 · K. Nogita, K. Une · Journal of Nuclear Materials · 171

Radiation-induced microstructural change in high burnup UO2 fuel pellets

1994 · K. Nogita, K. Une · Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms · 141

Cracking and relocation behavior of nuclear fuel pellets during rise to power

1983 · Masaomi Oguma · Nuclear Engineering and Design · 122

Microstructural change and its influence on fission gas release in high burnup UO2 fuel

1992 · K. Une, K. Nogita, et al. · Journal of Nuclear Materials · 119

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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Evolution of Microstructure and Microchemistry in Cold-worked 316 Stainless Steels under PWR Irradiation

2006 · Koji FUKUYA, Katsuhiko FUJII, et al. · Journal of Nuclear Science and Technology · 101

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High resolution TEM observation and density estimation of Xe bubbles in high burnup UO2 fuels

1998 · K Nogita, K Une · Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms · 91

Thermal Conductivity of UO2-BeO Pellet

1996 · Shinji ISHIMOTO, Mutsumi HIRAI, et al. · Journal of Nuclear Science and Technology · 91

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Neutron irradiation effects on intermetallic precipitates in Zircaloy as a function of fluence

1993 · Y. Etoh, S. Shimada · Journal of Nuclear Materials · 89

Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan

2021 · K. Sakamoto, Y. Miura, et al. · Journal of Nuclear Materials · 86

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An Assessment of the Fuel Pulverization Threshold During LOCA-Type Temperature Transients

2015 · J. A. Turnbull, S. K. Yagnik, et al. · Nuclear Science and Engineering · 85

Rim structure formation and high burnup fuel behavior of large-grained UO2 fuels

2000 · K Une, M Hirai, et al. · Journal of Nuclear Materials · 81

Fission Gas Release during Post Irradiation Annealing of BWR Fuels

1990 · Katsumi UNE, Shinji KASHIBE · Journal of Nuclear Science and Technology · 79

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Thermodynamic properties of nonstoichiometric urania-gadolinia solid solutions in the temperature range 700–1100° C

1982 · K. Une, M. Oguma · Journal of Nuclear Materials · 77

Effect of additives (Cr2O3, Al2O3, SiO2, MgO) on diffusional release of from UO2 fuels

1998 · S Kashibe, K Une · Journal of Nuclear Materials · 76

Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage

2008 · Masaki Aomi, Toshikazu Baba, et al. · Journal of ASTM International · 70

Effects of additives and the oxygen potential on the fission gas diffusion in UO2 fuel

1987 · Katsumi Une, Isami Tanabe, et al. · Journal of Nuclear Materials · 69

Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions

2017 · Y. Yano, T. Tanno, et al. · Journal of Nuclear Materials · 68

Oxygen potentials of (U, Gd)O2 ± x solid solutions in the temperature range 1000–1500°C

1983 · K. Une, M. Oguma · 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

Effects of zirconium and oxygen on the oxidation of FeCrAl-ODS alloys under air and steam conditions up to 1500 °C

2019 · T. Maeda, S. Ukai, et al. · Journal of Nuclear Materials · 66

Separation of Microstructural and Microchemical Effects in Irradiation Assisted Stress Corrosion Cracking using Post-irradiation Annealing

2004 · Koji FUKUYA, Morihito NAKANO, et al. · Journal of Nuclear Science and Technology · 64

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Microstructure and texture evolution and ring-tensile properties of recrystallized FeCrAl ODS cladding tubes

2019 · S.M.S. Aghamiri, T. Sowa, et al. · Materials Science and Engineering A · 63

Microstructure Effects on Fracture Strength of U02Fuel Pellets

1982 · Masaomi OGUMA · Journal of Nuclear Science and Technology · 63

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Works count: 448

Citation count: 13,480