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Yukihide Mori

Observed names: Mori, Yukihide, Y. Mori, Yukihide MORI
OpenAlex ID: A5006373572
Fuel failure and fission gas release in high burnup PWR fuels under RIA conditions
1997 · Toyoshi Fuketa, Hideo Sasajima, et al. · Journal of Nuclear Materials · 64
A study on the technique of spent fuel reprocessing with supercritical fluid direct extraction method (Super-DIREX method)
2002 · Takashi Shimada, Shinya Ogumo, et al. · Journal of Nuclear Science and Technology · 23
Stoichiometric Relation for Extraction of Uranium from UO2Powder using TBP Complex with HNO3and H2O in Supercritical CO2
2005 · Kayo SAWADA, Kazuyoshi URUGA, et al. · Journal of Nuclear Science and Technology · 22
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New results from the NSRR experiments with high burnup fuel
1996 · Toyoshi Fuketa, Brookhaven National Lab., Upton, NY (United States), et al. · 16
Behavior of high burnup PWR fuel under a simulated RIA condition in the NSRR
1996 · Toyoshi FUKETA, Yukihide Mori, et al. · 13
Stoichiometric Relation for Extraction of Uranium from UO2 Powder using TBP Complex with HNO3 and H2O in Supereritical CO2
2005 · Kayo SAWADA, Kazuyoshi URUGA, et al. · Journal of Nuclear Science and Technology · 6
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A Study on the dry pyrochemical technique for the oxide fuel decladding
2002 · Yuji Kosaka, Kunihiro Itoh, et al. · Journal of Nuclear Science and Technology · 4
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Densities of Supercritical Fluids Containing CO2and Tri-n-butylphosphate
2006 · Kayo SAWADA, Osamu TOMIOKA, et al. · Journal of Nuclear Science and Technology · 3
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Behavior of irradiated PWR fuel under a simulated RIA condition. Results of NSRR Test MH-3
1995 · Hideo Sasajima, Toyoshi FUKETA, et al. · 3
Direct Extraction of Uranium and Plutonium with Supercritical Carbon Dioxide from Mox Fuel
2006 · S. Ogumo, T. Shimada, et al. · Royal Society of Chemistry eBooks · 1
Development of Spent Fuel Reprocessing by Super-critical Fluid : Development of Super DIREX Method
2000 · Takashi SHIMADA, Shinya OGUMO, et al. · Doryoku, Enerugi Gijutsu Shinpojiumu koen ronbunshu/Doryoku, enerugi gijutsu no saizensen koen ronbunshu · 1
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Long-Term Perspective: Significance of Fast Reactor Development
2018 · Yukihide Mori · Atomic Energy Society of Japan
The effect evaluation of cooling rate on fuel debris (1) - the effect of cooling rate on debris microstructure
2013 · Noritaka Kogawa, Shigeru Kurematsu, et al.
The effect evaluation of cooling rate on fuel debris (2) - the effect of cooling rate for mechanical and dissolution properties on fuel debris
2013 · Shigeru Kurematsu, Noritaka Kogawa, et al.
Study on Reprocessing Plant for the Transition Period from LWR to FBRConcept for the Next Reprocessing Plant from the Viewpoint of Plutonium Supply and Demand
2011 · Takashi SHIMADA, Minefumi MATSUI, et al. · Transactions of the Atomic Energy Society of Japan
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Mitsubishi Activities for Nuclear Fuel Cycle Development
2008 · Hiroshi Sagawa, Yukihide Mori, et al.
Densities of Supercritical Fluids Containing CO2 and Tri-n-butylphosphate
2006 · Kayo SAWADA, Osamu TOMIOKA, et al. · Journal of Nuclear Science and Technology
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アミド系抽出剤を用いたウラン酸化物の溶解試験
2004 · Mizuno, Mineo, Kosaka, Yuji, et al. · Institutional Repositories DataBase (IRDB)
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Conceptual Design Study on Fast Reactor Fuel Reprocessing System Using Super-DIREX Process
2004 · Takeshi Takata, Yoshikazu Koma, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
The dissolving test of the uranium oxide using amide system extraction solvent
2004 · Mizuno Mineo, Yuji Kosaka, et al.
金属燃料製造設備構成の調査
2003 · Senda, Yasuhide, Mori, Yukihide · Institutional Repositories DataBase (IRDB)
Research on plant of metal fuel fabrication using casting process
2003 · Yasuhide Senda, Yukihide Mori
Tbp-硝酸溶媒へのウラン酸化物の溶解
2002 · Mori, Yukihide, Shimada, Takashi, et al. · Institutional Repositories DataBase (IRDB)
Dissolution of uranium oxide TBP-HNO 3 complex
2002 · Mizuno Mineo, Yuji Kosaka, et al.
Works count: 24
Citation count: 156
H-index: 6
I10-index: 5
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