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2001

Journal Article

Thermal conductivities of irradiated UO2 and (U,Gd)O-2

Minato, K., Shiratori, T., Serizawa, H., Hayashi, K., Une, K., Nogita, K., Hirai, M. and Amaya, M. (2001). Thermal conductivities of irradiated UO2 and (U,Gd)O-2. Journal of Nuclear Materials, 288 (1), 57-65. doi: 10.1016/S0022-3115(00)00578-X

Thermal conductivities of irradiated UO2 and (U,Gd)O-2

2001

Journal Article

Modification of Al-Si alloys with Ba, Ca, Y and Yb

Knuutinen, A., Nogita, K., McDonald, S. D. and Dahle, A. K. (2001). Modification of Al-Si alloys with Ba, Ca, Y and Yb. Journal of Light Metals, 1 (4), 229-240. doi: 10.1016/S1471-5317(02)00004-4

Modification of Al-Si alloys with Ba, Ca, Y and Yb

2001

Journal Article

Irradiation-induced microstructure change and fuel performance of high burn-up LWR fuels

Kashibe, S., Nogita, K. and Une, K. (2001). Irradiation-induced microstructure change and fuel performance of high burn-up LWR fuels. Journal of Nuclear Science and Technology, 288, 280-280.

Irradiation-induced microstructure change and fuel performance of high burn-up LWR fuels

2001

Journal Article

Eutectic solidification mode in sodium modified Al-7 mass %Si-3.5 mass %Cu-0.2 mass %Mg casting alloys

Nogita, K., McDonald, S. D., Zindel, J. W. and Dahle, A. K. (2001). Eutectic solidification mode in sodium modified Al-7 mass %Si-3.5 mass %Cu-0.2 mass %Mg casting alloys. Materials Transactions, 42 (9), 1981-1986. doi: 10.2320/matertrans.42.1981

Eutectic solidification mode in sodium modified Al-7 mass %Si-3.5 mass %Cu-0.2 mass %Mg casting alloys

2000

Journal Article

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

Une, K., Hirai, M., Nogita, K., Hosokawa, T., Suzawa, Y., Shimizu, S. and Etoh, Y. (2000). Rim structure formation and high burnup fuel behavior of large-grained UO2 fuels. Journal of Nuclear Materials, 278 (1), 54-63. doi: 10.1016/S0022-3115(99)00214-7

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

1999

Journal Article

Depth profiles of damage accumulation in UO2 and (U,Gd)O2 pellets irradiated with 100 MeV iodine

Nogita, K., Hayashi, K., Une, K. and Fukuda, K. (1999). Depth profiles of damage accumulation in UO2 and (U,Gd)O2 pellets irradiated with 100 MeV iodine. Journal of Nuclear Materials, 273 (3), 302-309. doi: 10.1016/S0022-3115(99)00048-3

Depth profiles of damage accumulation in UO2 and (U,Gd)O2 pellets irradiated with 100 MeV iodine

1998

Journal Article

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

Nogita, K. and Une, K. (1998). High resolution TEM observation and density estimation of Xe bubbles in high burnup UO2 fuels. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 141 (1-4), 481-486. doi: 10.1016/S0168-583X(98)00040-8

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

1997

Journal Article

Effect of grain size on recrystallization in high burnup fuel pellets

Nogita, K., Une, K., Hirai, M., Ito, K., Ito, K. and Shirai, Y. (1997). Effect of grain size on recrystallization in high burnup fuel pellets. Journal of Nuclear Materials, 248, 196-203. doi: 10.1016/S0022-3115(97)00156-6

Effect of grain size on recrystallization in high burnup fuel pellets

1997

Journal Article

High resolution TEM of high burnup UO2 fuel

Nogita, K. and Une, K. (1997). High resolution TEM of high burnup UO2 fuel. Journal of Nuclear Materials, 250 (2-3), 244-249. doi: 10.1016/S0022-3115(97)00282-1

High resolution TEM of high burnup UO2 fuel

1997

Journal Article

Formation of pellet-cladding bonding layer in high burnup BWR fuels)

Nogita, Kazuhiro and Une, Katsumi (1997). Formation of pellet-cladding bonding layer in high burnup BWR fuels). Journal of Nuclear Science and Technology, 34 (7), 679-686. doi: 10.1080/18811248.1997.9733726

Formation of pellet-cladding bonding layer in high burnup BWR fuels)

1996

Journal Article

TEM analysis of pellet-cladding bonding layer in high burnup BWR fuel

Nogita, K., Une, K. and Korei, Y. (1996). TEM analysis of pellet-cladding bonding layer in high burnup BWR fuel. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 116 (1-4), 521-526. doi: 10.1016/0168-583X(96)00100-0

TEM analysis of pellet-cladding bonding layer in high burnup BWR fuel

1995

Journal Article

Corrosion behavior of unirradiated oxide fuel pellets in high temperature water

Une, K., Kashibe, S. and Nogita, K. (1995). Corrosion behavior of unirradiated oxide fuel pellets in high temperature water. Journal of Nuclear Materials, 227 (1-2), 32-39. doi: 10.1016/0022-3115(95)00141-7

Corrosion behavior of unirradiated oxide fuel pellets in high temperature water

1995

Journal Article

Irradiation-induced recrystallization in high burnup UO2 fuel

Nogita, K. and Une, K. (1995). Irradiation-induced recrystallization in high burnup UO2 fuel. Journal of Nuclear Materials, 226 (3), 302-310. doi: 10.1016/0022-3115(95)00123-9

Irradiation-induced recrystallization in high burnup UO2 fuel

1994

Journal Article

Radiation-induced microstructural change in high burnup UO2 fuel pellets

Nogita, K. and Une, K. (1994). Radiation-induced microstructural change in high burnup UO2 fuel pellets. Nuclear Inst. and Methods in Physics Research, B, 91 (1-4), 301-306. doi: 10.1016/0168-583X(94)96235-9

Radiation-induced microstructural change in high burnup UO2 fuel pellets

1994

Journal Article

Effect of Grain Size on Microstructural Change and Damage Recovery in UO2 Fuels Irradiated to 23 GWd/t

Nogita, Kazuhiro and Une, Katsumi (1994). Effect of Grain Size on Microstructural Change and Damage Recovery in UO2 Fuels Irradiated to 23 GWd/t. Journal of Nuclear Science and Technology, 31 (9), 929-936. doi: 10.1080/18811248.1994.9735243

Effect of Grain Size on Microstructural Change and Damage Recovery in UO2 Fuels Irradiated to 23 GWd/t

1994

Journal Article

Effect of Grain Size on Microstructural Change and Damage Recovery in UO2Fuels Irradiated to 23GWd/t

Nogita, Kazuhiro and Une, Katsumi (1994). Effect of Grain Size on Microstructural Change and Damage Recovery in UO2Fuels Irradiated to 23GWd/t. Journal of Nuclear Science and Technology, 31 (9), 929-936. doi: 10.3327/jnst.31.929

Effect of Grain Size on Microstructural Change and Damage Recovery in UO2Fuels Irradiated to 23GWd/t

1993

Journal Article

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

Kashibe, S., Une, K. and Nogita, K. (1993). Formation and growth of intragranular fission gas bubbles in UO2 fuels with burnup of 6-83 GWd/t. Journal of Nuclear Materials, 206 (1), 22-34. doi: 10.1016/0022-3115(93)90229-R

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

1993

Journal Article

Thermal recovery of radiation defects and microstructural change in irradiated UO2fuels

Nogita, Kazuhiro and Une, Katsumi (1993). Thermal recovery of radiation defects and microstructural change in irradiated UO2fuels. Journal of Nuclear Science and Technology, 30 (9), 900-910. doi: 10.1080/18811248.1993.9734564

Thermal recovery of radiation defects and microstructural change in irradiated UO2fuels

1993

Journal Article

Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO2 Fuels

Nogita, Kazuhiro and Une, Katsumi (1993). Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO2 Fuels. Journal of Nuclear Science and Technology, 30 (9), 900-910. doi: 10.3327/jnst.30.900

Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO2 Fuels

1992

Journal Article

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

Une, K., Nogita, K., Kashibe, S. and Imamura, M. (1992). Microstructural change and its influence on fission gas release in high burnup UO2 fuel. Journal of Nuclear Materials, 188 (C), 65-72. doi: 10.1016/0022-3115(92)90455-T

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