JOPSS - Search Results

Journal Articles

Thermodynamics of the UO $_{2}$ solid solution with magnesium and europium oxides

Fujino, Takeo*; Sato, Nobuaki*; Yamada, Kota*; Nakama, Shohei*; Fukuda, Kosaku; Serizawa, Hiroyuki; Shiratori, Tetsuo*

Journal of Nuclear Materials, 297(3), p.332 - 340, 2001/09

https://doi.org/10.1016/S0022-3115(01)00627-4

Times Cited Count：4 Percentile：33.07(Materials Science, Multidisciplinary)

Oxygen potential of solid solution Mg $_{y}$ Eu $_{z}$ U $_{1-y-z}$ O $_{2+x}$ was examined as a function of O/Metal ratio at 1000, 1100 and 1200 $^{circ}$ C. The O/Metal ratio which gave the steepest change of the oxygen potential(GOM) was 1.995 for y=0.05, z=0.1 and y=0.05, z=0.05. The position decreased to 1.908 at higher Mg $^{2+}$ concentration of y=0.1, z=0.05. The GOM did not change with temperature in a range 1000-1200 $^{circ}$ C. At GOM, a friction of 0.473 of total Mg $^{2+}$ occupy the interstitial position of the fluorite lattice.

Journal Articles

Post-irradiation examination of high burnup Mg doped UO $_{2}$ in comparison with undoped UO $_{2}$ , Mg-Nb doped UO $_{2}$ and Ti doped UO $_{2}$

Fujino, Takeo*; Shiratori, Tetsuo; Sato, Nobuaki*; Fukuda, Kosaku; Yamada, Kota*; Suzuki, Yasufumi; Serizawa, Hiroyuki

Journal of Nuclear Materials, 297(2), p.176 - 205, 2001/08

https://doi.org/10.1016/S0022-3115(01)00609-2

Times Cited Count：23 Percentile：81.73(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Oxygen potential and defect structure of the solid solution, Mg-Gd-UO $_{2}$

Fujino, Takeo*; Sato, Nobuaki*; Yamada, Kota*; Okazaki, Manabu*; Fukuda, Kosaku; Serizawa, Hiroyuki; Shiratori, Tetsuo*

Journal of Nuclear Materials, 289(3), p.270 - 280, 2001/03

https://doi.org/10.1016/S0022-3115(01)00427-5

Times Cited Count：2 Percentile：19.32(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

High burnup performance of Mg, Mg-Nb and Ti doped UO $_{2}$ fuels

Shiratori, Tetsuo; Serizawa, Hiroyuki; Fukuda, Kosaku; Fujino, Takeo*; Sato, Nobuaki*; Yamada, Kota*

JAERI-Research 2000-045, 74 Pages, 2000/09

JAERI-Research-2000-045.pdf:8.19MB

no abstracts in English

JAEA Reports

Irradiation experiments of the 13th-15th OGL-1 fuel assemblies

Hayashi, Kimio; Sawa, Kazuhiro; Shiratori, Tetsuo; Kikuchi, Hironobu; Fukuda, Kosaku; Kitajima, Toshio; Ito, Tadaharu; Waragai, Hyota

JAERI-Research 2000-001, p.116 - 0, 2000/01

JAERI-Research-2000-001.pdf:21.78MB

no abstracts in English

Journal Articles

Radiation damage in UO $_{2}$ bombarded with iodine and nickel ions at energies around 100 MeV

Hayashi, Kimio; ; Fukuda, Kosaku

Advances in Science and Technology, 24, p.439 - 446, 1999/00

no abstracts in English

Journal Articles

Oxygen potential of solid solution Eu $_{y}$ U $_{1-y}$ O $_{2+x}$

Fujino, Takeo*; Sato, Nobuaki*; Yamada, Kota*; ; Fukuda, Kosaku; Serizawa, Hiroyuki; Shiratori, Tetsuo

Journal of Nuclear Materials, 265(1-2), p.154 - 160, 1999/00

https://doi.org/10.1016/S0022-3115(98)00502-9

Times Cited Count：6 Percentile：45.06(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Development of advanced fabrication technology for high-temperature gas-cooled reactor fuel; Reduction of coating failure fraction

Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; Yoshimuta, Shigeharu*; ; ; ;

JAERI-Research 98-070, 25 Pages, 1998/11

JAERI-Research-98-070.pdf:2.18MB

no abstracts in English

Journal Articles

Thermal expansion and thermal conductivity of cesium uranates

Takano, Masahide; Minato, Kazuo; Fukuda, Kosaku; Sato, Seichi*; Ohashi, Hiroshi*

Journal of Nuclear Science and Technology, 35(7), p.485 - 493, 1998/07

https://doi.org/10.3327/jnst.35.485

Times Cited Count：4 Percentile：38.47(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

HRB-22 capsule irradiation test for HTGR fuel; JAERI/USDOE collaborative irradiation test

Minato, Kazuo; Sawa, Kazuhiro; Fukuda, Kosaku; Baldwin, C. A.*; Gabbard, W. A.*; O.F.Kimball*; Malone, C. M.*; F.C.Montgomery*; B.F.Myers*; N.H.Packan*

JAERI-Research 98-021, 187 Pages, 1998/03

JAERI-Research-98-021.pdf:13.23MB

no abstracts in English

Journal Articles

Thermal conductivity of technetium

Minato, Kazuo; Serizawa, Hiroyuki; Fukuda, Kosaku

Journal of Alloys and Compounds, 267, p.274 - 278, 1998/00

https://doi.org/10.1016/S0925-8388(97)00514-8

Times Cited Count：7 Percentile：49.44(Chemistry, Physical)

no abstracts in English

Journal Articles

Unusual variation of temperature factor of uranium dioxide at high temperature

Serizawa, Hiroyuki; Fukuda, Kosaku; Shiratori, Tetsuo; Fujino, Takeo*; Sato, Nobuaki*; Yamada, Kota*

Journal of Alloys and Compounds, 271-273, p.386 - 390, 1998/00

https://doi.org/10.1016/S0925-8388(98)00095-4

Times Cited Count：9 Percentile：54.62(Chemistry, Physical)

no abstracts in English

Journal Articles

Thermal expansion and thermal conductivity of Cs $_{2}$ CrO $_{4}$

Takano, Masahide; Minato, Kazuo; Fukuda, Kosaku; Sato, Seichi*; Ohashi, Hiroshi*

Journal of Alloys and Compounds, 278, p.277 - 282, 1998/00

https://doi.org/10.1016/S0925-8388(98)00595-7

Times Cited Count：1 Percentile：19.35(Chemistry, Physical)

no abstracts in English

Journal Articles

Deterioration of ZrC-coated fuel particle caused by failure of pyrolytic carbon layer

Minato, Kazuo; Fukuda, Kosaku; Sekino, Hajime; Ishikawa, Akiyoshi;

Journal of Nuclear Materials, 252, p.13 - 21, 1998/00

https://doi.org/10.1016/S0022-3115(97)00319-X

no abstracts in English

JAEA Reports

Energy transfer and thermal conductivity through inert matrix and nuclear fuel analogous materials

C.Degueldre*; Takano, Masahide; Omichi, Toshihiko; Fukuda, Kosaku; P.Heimgartner*; T.Graber*

JAERI-Research 97-087, 19 Pages, 1997/11

JAERI-Research-97-087.pdf:0.87MB

no abstracts in English

JAEA Reports

Sample preparation and characterization of technetium metal

Minato, Kazuo; Serizawa, Hiroyuki; Fukuda, Kosaku; Ito, Mitsuo

JAERI-Research 97-077, 17 Pages, 1997/10

JAERI-Research-97-077.pdf:1.09MB

no abstracts in English

Journal Articles

An Investigation of cesium release from coated particle fuel of the High-Temperature Gas-cooled Reactor

Sawa, Kazuhiro; Minato, Kazuo; Tobita, Tsutomu*; Fukuda, Kosaku

Nuclear Technology, 118(2), p.123 - 131, 1997/05

https://doi.org/10.13182/NT97-A35372

Times Cited Count：1 Percentile：14.29(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Thermochemical evaluation and preparation of cesium uranates

Takano, Masahide; Minato, Kazuo; Fukuda, Kosaku; Sato, Seichi*; Ohashi, Hiroshi*

JAERI-Research 97-021, 19 Pages, 1997/03

JAERI-Research-97-021.pdf:0.74MB

no abstracts in English

Journal Articles

Improvements in quality of as-manufactured fuels for high-temperature gas-cooled reactors

Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; ; ; ;

Journal of Nuclear Science and Technology, 34(3), p.325 - 333, 1997/03

https://doi.org/10.3327/jnst.34.325

Times Cited Count：16 Percentile：75.26(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal expansion and thermal conductivity of cesium molybdate

Minato, Kazuo; Takano, Masahide; Fukuda, Kosaku; Sato, Seichi*; Ohashi, Hiroshi*

Journal of Alloys and Compounds, 255, p.18 - 23, 1997/00

https://doi.org/10.1016/S0925-8388(96)02841-1

Times Cited Count：14 Percentile：66.41(Chemistry, Physical)

no abstracts in English

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Thermodynamics of the UO $_{2}$ solid solution with magnesium and europium oxides

Post-irradiation examination of high burnup Mg doped UO $_{2}$ in comparison with undoped UO $_{2}$ , Mg-Nb doped UO $_{2}$ and Ti doped UO $_{2}$

Oxygen potential and defect structure of the solid solution, Mg-Gd-UO $_{2}$

High burnup performance of Mg, Mg-Nb and Ti doped UO $_{2}$ fuels

Irradiation experiments of the 13th-15th OGL-1 fuel assemblies

Radiation damage in UO $_{2}$ bombarded with iodine and nickel ions at energies around 100 MeV

Oxygen potential of solid solution Eu $_{y}$ U $_{1-y}$ O $_{2+x}$

Development of advanced fabrication technology for high-temperature gas-cooled reactor fuel; Reduction of coating failure fraction

Thermal expansion and thermal conductivity of cesium uranates

HRB-22 capsule irradiation test for HTGR fuel; JAERI/USDOE collaborative irradiation test

Thermal conductivity of technetium

Unusual variation of temperature factor of uranium dioxide at high temperature

Thermal expansion and thermal conductivity of Cs $_{2}$ CrO $_{4}$

Deterioration of ZrC-coated fuel particle caused by failure of pyrolytic carbon layer

Energy transfer and thermal conductivity through inert matrix and nuclear fuel analogous materials

Sample preparation and characterization of technetium metal

An Investigation of cesium release from coated particle fuel of the High-Temperature Gas-cooled Reactor

Thermochemical evaluation and preparation of cesium uranates

Improvements in quality of as-manufactured fuels for high-temperature gas-cooled reactors

Thermal expansion and thermal conductivity of cesium molybdate