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Hirooka, Shun; Horii, Yuta; Sunaoshi, Takeo*; Uno, Hiroki*; Yamada, Tadahisa*; Vauchy, R.; Hayashizaki, Kohei; Nakamichi, Shinya; Murakami, Tatsutoshi; Kato, Masato
Journal of Nuclear Science and Technology, 60(11), p.1313 - 1323, 2023/11
Times Cited Count:5 Percentile:78.63(Nuclear Science & Technology)Additive MOX pellets are fabricated by a conventional dry powder metallurgy method. NdO
and Sm
O
are chosen as the additive materials to simulate the corresponding soluble fission products dispersed in MOX. Shrinkage curves of the MOX pellets are obtained by dilatometry, which reveal that the sintering temperature is shifted toward a value higher than that of the respective regular MOX. The additives, however, promote grain growth and densification, which can be explained by the effect of oxidized uranium cations covering to a pentavalent state. Ceramography reveals large agglomerates after sintering, and Electron Probe Micro-Analysis confirms that inhomogeneous elemental distribution, whereas XRD reveals a single face-centered cubic phase. Finally, by grinding and re-sintering the specimens, the cation distribution homogeneity is significantly improved, which can simulate spent nuclear fuels with soluble fission products.
Wang, J.*; Otobe, Haruyoshi; Nakamura, Akio; Takeda, Masuo*
Journal of Solid State Chemistry, 176(1), p.105 - 110, 2003/11
Times Cited Count:14 Percentile:43.66(Chemistry, Inorganic & Nuclear)no abstracts in English
Wang, J.*; Nakamura, Akio; Takeda, Masuo*
Solid State Ionics, 164(3-4), p.185 - 191, 2003/11
Times Cited Count:36 Percentile:79.79(Chemistry, Physical)no abstracts in English
; Nishino, Yasuharu; Yamahara, Takeshi;
Proc. of 43rd Conf. on Robotics and Remote Systems 1995, 0, p.75 - 80, 1996/00
no abstracts in English
; Nishino, Yasuharu; Yamahara, Takeshi;
Transactions of the American Nuclear Society, 73, p.465 - 466, 1995/00
no abstracts in English
Kang, T.-K.*; Kuk, I.-H.*; Katano, Yoshio; Igawa, Naoki; Ono, Hideo
Journal of Nuclear Materials, 209(3), p.321 - 325, 1994/05
no abstracts in English
Kimura, Takaumi; Choppin, G. R.*
Journal of Alloys and Compounds, 213-214, p.313 - 317, 1994/00
Times Cited Count:273 Percentile:99.70(Chemistry, Physical)no abstracts in English
T.Kang*; Nagasaki, Takanori; Igawa, Naoki; K.Il-Hium*; Ono, Hideo
Journal of the American Ceramic Society, 75(8), p.2297 - 2299, 1992/08
Times Cited Count:17 Percentile:67.60(Materials Science, Ceramics)no abstracts in English
;
JAERI-M 85-208, 53 Pages, 1986/01
no abstracts in English
;
Mater.Res.Bull., 21, p.1343 - 1349, 1986/00
Times Cited Count:31 Percentile:79.48(Materials Science, Multidisciplinary)no abstracts in English
;
Environ.Exp.Bot., 24(4), p.369 - 375, 1984/00
Times Cited Count:0 Percentile:0.00(Plant Sciences)no abstracts in English
;
Environ.Exp.Bot., 23(4), p.361 - 364, 1983/00
Times Cited Count:2 Percentile:22.10(Plant Sciences)no abstracts in English
Tachikawa, Enzo;
Journal of Inorganic and Nuclear Chemistry, 38(2), p.193 - 196, 1976/02
Times Cited Count:15no abstracts in English
Tachikawa, Enzo;
Bulletin of the Chemical Society of Japan, 48(7), p.2182 - 2184, 1975/07
Times Cited Count:6no abstracts in English
Journal of Nuclear Science and Technology, 1(6), p.193 - 196, 1964/00
no abstracts in English
Akashi, Masatoshi; Hirooka, Shun; Watanabe, Masashi; Komeno, Akira; Morimoto, Kyoichi
no journal, ,
Uranium oxide fuels containing GdO
had been used to control fuel power in reactors of the Fukushima Daiichi Nuclear Power Plant where the severe accident occurred in 2011. JAEA has been evaluating physical properties of the molten fuel debris in the damaged core. However physical properties of the fuel debris containing Gd are not known, hence it is very difficult to select an appropriate debris removal method. Especially, it is important to know the distribution of Gd in the molten fuels for the evaluation of nuclear criticality safety during removal work. In this study, simulated samples of the molten fuel debris, which consisted of ZrO
, UO
and Gd
O
, were prepared and their properties, which are density, crystal structure, thermal conductivity, thermal expansion and melting temperature, were investigated. This study includes results obtained under the research program entrusted to International Research Institute for Nuclear Decommissioning including Japan Atomic Energy Agency by Agency for Natural Resources and Energy, Ministry of Economy, Trade and Industry (METI) of Japan.