An investigation into dissolution rate of spent nuclear fuel in aqueous reprocessingMINEO, Hideaki; ISOGAI, Hikaru; MORITA, Yasuji et al.Journal of Nuclear Science and Technology. 2004, Vol 41, Num 2, pp 126-134, issn 0022-3131, 9 p.Article

Fission products release from irradiated FBR MOX fuel during transient conditionsSATO, Isamu; NAKAGIRI, Toshio; HIROSAWA, Takashi et al.Journal of Nuclear Science and Technology. 2003, Vol 40, Num 2, pp 104-113, issn 0022-3131, 10 p.Article

Application of X-ray computer tomography for observing the deflection and displacement of fuel pins in an assembly irradiated in FBRKATSUYAMA, Kozo; NAGAMINE, Tsuyoshi; MATSUMOTO, Shin-Ichiro et al.Journal of Nuclear Science and Technology. 2003, Vol 40, Num 4, pp 220-226, issn 0022-3131, 7 p.Article

Corrosion of steels in lead-bismuth flowKONDO, Masatoshi; TAKAHASHI, Minoru; SAWADA, Naoki et al.Journal of Nuclear Science and Technology. 2006, Vol 43, Num 2, pp 107-116, issn 0022-3131, 10 p.Article

Separation of actinides from rare earth elements by means of molten salt electrorefining with anodic dissolution of U-Pu-Zr alloy fuelKINOSHITA, Kensuke; KOYAMA, Tadafumi; INOUE, Tadashi et al.The Journal of physics and chemistry of solids. 2005, Vol 66, Num 2-4, pp 619-624, issn 0022-3697, 6 p.Conference Paper

Transport criticality analysis of FBR MONJU initial critical core in whole core simulation by NSHEX and GMVPTODOROVA, Galina; NISHI, Hiroshi; ISHIBASHI, Junichi et al.Journal of Nuclear Science and Technology. 2004, Vol 41, Num 4, pp 493-501, issn 0022-3131, 9 p.Article

Development of 160 m³/min large capacity sodium-immersed self-cooled electromagnetic pumpOTA, Hiroyuki; KATSUKI, Kenji; FUNATO, Minoru et al.Journal of Nuclear Science and Technology. 2004, Vol 41, Num 4, pp 511-523, issn 0022-3131, 13 p.Article

Thermal conductivities of granular UO₂ compacts with/without uranium particlesISHII, Tetsuya; YUDA, Ryoichi; HIRAI, Mutsumi et al.Journal of Nuclear Science and Technology. 2004, Vol 41, Num 12, pp 1204-1210, issn 0022-3131, 7 p.Article

Measurement of burnup in FBR MOX fuel irradiated to high burnupKOYAMA, Shin-Ichi; OSAKA, Masahiko; SEKINE, Takashi et al.Journal of Nuclear Science and Technology. 2003, Vol 40, Num 12, pp 998-1013, issn 0022-3131, 16 p.Article

Analysis of overheating rupture in heat-transfer tubes causing corrosive high-temperature reactionHAMADA, Hirotsugu; TANABE, Hiromi.Journal of Nuclear Science and Technology. 2004, Vol 41, Num 6, pp 665-672, issn 0022-3131, 8 p.Article

Development of a Performance Analysis Code for Vibro-Packed MOX FuelsISHII, Tetsuya; NEMOTO, Junichi; ASAGA, Takeo et al.Journal of Nuclear Science and Technology. 2008, Vol 45, Num 4, pp 263-273, issn 0022-3131, 11 p.Article

Thermal and mechanical properties of uranium nitride prepared by SPS techniqueMUTA, Hiroaki; KUROSAKI, Ken; UNO, Masayoshi et al.Journal of materials science. 2008, Vol 43, Num 19, pp 6429-6434, issn 0022-2461, 6 p.Conference Paper