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Takashi Hirosawa

Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor
2008 · Kosuke Tanaka, Shuhei Miwa, et al. · Journal of Nuclear Materials · 37
Melting temperature and thermal conductivity of irradiated mixed oxide fuel
1993 · K. Yamamoto, T. Hirosawa, et al. · Journal of Nuclear Materials · 33
Fission Products Release from Irradiated FBR MOX Fuel during Transient Conditions
2003 · Isamu SATO, Toshio NAKAGIRI, et al. · Journal of Nuclear Science and Technology · 32
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Thermal conductivity of BaPuO3 at temperatures from 300 to 1500 K
2011 · Kosuke Tanaka, Isamu Sato, et al. · Journal of Nuclear Materials · 30
Melting Temperature of Mixed Oxide Fuels for Fast Reactors
2002 · Koichi KONNO, Takashi HIROSAWA · Journal of Nuclear Science and Technology · 24
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Burnup dependence of melting temperature of FBR mixed oxide fuels irradiated to high burnup
2011 · Takashi Hirosawa, Isamu Sato · Journal of Nuclear Materials · 16
Melting Temperature of Simulated High-Burnup Mixed Oxide Fuels for Fast Reactors
1999 · Koichi KONNO, Takashi HIROSAWA · Journal of Nuclear Science and Technology · 16
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Melting Temperature of Irradiated Fast Reactor Mixed Oxide Fuels
1998 · Koichi KONNO, Takashi HIROSAWA · Journal of Nuclear Science and Technology · 13
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Thermophysical properties of perovskite type alkaline-earth metals and plutonium complex oxides
2012 · Kosuke Tanaka, Isamu Sato, et al. · Journal of Nuclear Materials · 10
Preparation and characterization of the simulated burnup americium-containing uranium–plutonium mixed oxide fuel
2011 · Kosuke Tanaka, Masahiko Osaka, et al. · Journal of Nuclear Materials · 8
Melting behavior of MgO-based inert matrix fuels containing (Pu,Am)O2−x
2010 · Shuhei Miwa, Isamu Sato, et al. · Journal of Nuclear Materials · 8
Development of HCl-free solid-phase extraction combined with ICP-MS/MS for rapid assessment of difficult-to-measure radionuclides. Part II: Highly sensitive monitoring of 126Sn in concrete rubble
2022 · Van-Khoai Do, Takahiro Furuse, et al. · Journal of Radioanalytical and Nuclear Chemistry · 6
Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior
2014 · Kosuke Tanaka, Shuhei Miwa, et al. · Journal of Nuclear Science and Technology · 6
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Research and Development of Americium-containing Mixed Oxide Fuel for Fast Reactors
2007 · Kosuke Tanaka, Masahiko Osaka, et al. · 6
Americium and plutonium release behavior from irradiated mixed oxide fuel during heating
2013 · I. Sato, M. Suto, et al. · Journal of Nuclear Materials · 5
Innovative oxide fuels doped with minor actinides for use in fast reactors
2007 · M. Osaka, S. Miwa, et al. · WIT transactions on ecology and the environment · 4
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High temperature behavior of irradiated mixed nitride fuel during heating tests
2007 · Isamu Sato, Kosuke Tanaka, et al. · Journal of Alloys and Compounds · 4
Thermophysical properties of americium-containing barium plutonate
2015 · Kosuke Tanaka, Isamu Sato, et al. · Journal of Nuclear Science and Technology · 2
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Release behavior of radionuclides from MOX fuels irradiated in a fast reactor during heating tests
2020 · K. Tanaka, I. Sato, et al. · Journal of Nuclear Materials · 1
Effect of fission products accumulation on thermophysical properties of oxide fuels for fast reactors
2012 · Kosuke Tanaka, Masahiko Osaka, et al.
Measurement of surface melting temperature with high-speed pyrometers by containerless method
2012 · Tatsumi Arima, Y. Kawauchi, et al. · Society of Instrument and Control Engineers of Japan
Melting temperature and thermal conductivity of irradiated (U,Pu)O[sub 2] fuel
1992 · Kazuya Yamamoto, Takashi Hirosawa, et al. · Transactions of the American Nuclear Society
Works count: 22
Citation count: 261
H-index: 9
I10-index: 9
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