JOPSS - Search Results

Journal Articles

Current status and development plan on fuel cycle system of fast reactor cycle technology in Japan

Ito, Masanori; Funasaka, Hideyuki; Namekawa, Takashi

Proceedings of European Nuclear Conference 2007 (ENC 2007) (CD-ROM), 7 Pages, 2007/09

The FaCT project in Japan is implemented purposing to decide the adoption of innovative technologies by 2010 and to judge the prospect of the applicability of innovative technologies to the commercialized fast reactor cycle system by 2015. Innovative technologies to be developed are identified as six development issues for advanced aqueous reprocessing system and six ones for simplified pelletizing method fuel fabrication system. As for reprocessing technology, uranium crystallization and extraction chromatography are important. Wide range of development work from chemical fundamental study to engineering-scale equipment operation are planned and practiced. As for fuel fabrication, conversion and granulation are important to get the source MOX powder with good flowability. Development of modular equipments with grater remote maintenance performance and repairing system in a hot cell is essential to put the low decontaminated TRU fuel fabrication into practical use.

Journal Articles

Current Status of PIE Activities in O-arai Engineering Center of JNC on FBR MOX Fuel

Koyama, Shinichi; Osaka, Masahiko; Namekawa, Takashi; Ito, Masahiko

Proceedings of 7th International Conference on Nuclear Criticality Safety (ICNC 2003), 0 Pages, 2003/10

Japan Nuclear Cycle Development Institute (JNC) is now totally promoting the development of commercialized fast reactors to realize stable supply of energy in future. One of the important items is to develop hign-performance fuel. For that purpose,it is e

Journal Articles

Measurement of Burn-up in FBR MOX Fuel Irradiated up to High Burn-up

Koyama, Shinichi; Osaka, Masahiko; Sekine, Takashi; Morozumi, Katsufumi; Namekawa, Takushi;

Journal of Nuclear Science and Technology, 40(2), p.998 - 1013, 2003/02

https://doi.org/10.3327/jnst.40.998

Times Cited Count：23 Percentile：80.7(Nuclear Science & Technology)

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Journal Articles

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Ukai, Shigeharu; Shikakura, Sakae; Sato, Yoshinori; Koyama, Shinichi; ;

Nihon Genshiryoku Gakkai-Shi, 36(5), 361 Pages, 1994/05

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Journal Articles

Development of Advanced Austenitic Stainless Steel for Fast Reactor Core Material

Shikakura, Sakae; Ukai, Shigeharu; Sato, Yoshinori; Harada, Makoto; Koyama, Shinichi; ; Nomura, Shigeo; Shibahara, Itaru

Nihon Genshiryoku Gakkai-Shi, 36(5), p.441 - 455, 1994/00

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JAEA Reports

Material strength standard of FBR grade type 316 stainless steel(Draft)

Watashi, Katsumi; Aoto, Kazumi; Aoki, M; Komine, Ryuji; Ito, Takushi; Hasebe, Shinichi; Kato, Shoichi; Koi, Mamoru; Wada, Yusaku

PNC TN9410 93-142, 120 Pages, 1993/06

PNC-TN9410-93-142.pdf:6.08MB

Much progress has been made in improving established creep properties of Type 316 stainless steel and to develop a new structural material named "FBR Grade Type 316 Stainless Steel", 316FR, with superior creep properties. This report includes a draft of Material Strength Standard of 316FR and its interpretation on the basis of the major result of research and development conducted so far. The draft includes identical items described in the "Standards for the Strength of Materials" for Monju, and was carefully prepared to have an identical style for convenience in design evaluation. Creep damage evaluation diagrams, which are depicted in the "Structural Design Guide for Class 1 Components of Prototype Fast Breeder Reactor for Elevated Temperature Service" (ETSDG) for individual materials, are also included in this report.

Journal Articles