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Watanabe, Masashi; Matsumoto, Taku; Hirooka, Shun; Morimoto, Kyoichi; Kato, Masato
2018 GIF Symposium Proceedings (Internet), p.315 - 320, 2020/05
Recently, a research group studying at Plutonium Fuel Development Facility (PFDF) in Japan Atomic Energy Agency has systematically measured vast amounts of physical properties in the non-stoichiometric (U, Pu)O. Lattice parameter, elastic modulus, thermal expansion, oxygen potential, oxygen chemical diffusion coefficient and thermal conductivity were successfully measured as function of Pu content, O/M ratio and temperature, and the effects of Pu content and O/M ratio on their physical properties were evaluated. In this work, those experimental data are reviewed, and latest experimental data set on the non-stoichiometric (U, Pu)O are presented. The data set would be available in development of a fuel performance code.
; *; Fukazawa, E.*; Yamamoto, H.*; Taira, K.*; Tanaka, Toshiyuki*; Suyama, Yasuhiro*; Kondo, Y.*; *; *; et al.
PNC TJ1100 97-002, 85 Pages, 1997/03
None
Toyohara, Masumitsu*; Hirayama, Fumio*; Tamura, Toshiyuki*; Fukazawa, Takuji*; Igarashi, Noboru*
PNC TJ8164 96-010, 213 Pages, 1996/03
no abstracts in English
Aoki, Kenji*; Hibiya, Keisuke*; Shiogama, Yukihiro*; Toida, Masaru*; Fukazawa, E.*; Okutsu, Kazuo*; *
PNC TJ1100 95-002, 195 Pages, 1995/03
None
Aoki, Kenji*; Hibiya, Keisuke*; Shiogama, Yukihiro*; Toida, Masaru*; Fukazawa, E.*; Taira, K.*; *
PNC TJ1100 95-001, 66 Pages, 1995/03
None
Hayashi, Hideyuki; Shikakura, Sakae; ; ; ; Otani, Tetsuo
PNC TN9410 93-066, 47 Pages, 1993/03
This report summarizes the results of the study on fuel design specifications for a large scale LMFBR in the fiscal year 1992. The items contained in the report are as follows; (1)Present status of the fuel development in PNC (2)R&Ds on the deformation of fuel subassemblies in PNC (3)Sufficiency of the strength data of PNC1520-steel in high temperature region
specimensTakano, Masahide; Nishi, Tsuyoshi; Sudo, Ayako
no journal, ,
For the removal operation of fuel debris of the Fukushima Daiichi Nuclear Power Plant, some material properties of sintered (U,Zr)O solid solution specimens were measured. Their heat capacity and thermal conductivity were determined in the temperature range from room temperature to 1073 K. Micro Vickers hardness and electrical resistivity were also measured at room temperature as a function of U fraction. In addition to these material properties, the correlation between phases and O/M ratios of U-Zr-O system under oxidizing conditions was investigated. In the (U,Zr)
hyperstoichiometric region, the hypothetical O/U ratio in the solid solution was found to be independent of either U fraction and crystal structure. Further, three orthorhombic phases in the U-Zr-O system under more oxidizing conditions were identified, and their phase relationship was successfully defined.
Kato, Masato
no journal, ,
no abstracts in English
Hirooka, Shun; Akashi, Masatoshi; Komeno, Akira; Morimoto, Kyoichi; Kato, Masato
no journal, ,
To understand physical property on the fuel debris generated in core melt accident at Fukushima Daiichi Nuclear Power Plan, oxidation test and thermal conductivity measurement with simulated fuel debris were performed. By using the data, the status of the fuel debris in the damaged cores were estimated.
