Citations (10)
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Read on this site (4)
Kazuya Ohgama, Toshiharu Hara, Hirokazu Ohta, Masayuki Naganuma, Shigeo Ohki & Masatoshi Iizuka. (2022) A design study on a metal fuel fast reactor core for high efficiency minor actinide transmutation by loading silicon carbide composite material. Journal of Nuclear Science and Technology 59:6, pages 735-747.
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Kazuya Ohgama, Yoshihiro Nakano & Shigeo Ohki. (2016) Analysis of fuel subassembly innerduct configurational effects on the core characteristics and power distribution of a sodium-cooled fast breeder reactor. Journal of Nuclear Science and Technology 53:8, pages 1155-1163.
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Kazuya Ohgama, Shigeo Ohki, Kazuteru Sugino & Tsutomu Okubo. (2014) Comparison and sensitivity analysis of the core characteristics of a sodium-cooled fast breeder reactor with 750 MWe output evaluated by JENDL-4.0 and ADJ2000R. Journal of Nuclear Science and Technology 51:4, pages 558-567.
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Shigeo Ohki, Masayuki Naganuma, Tsutomu Okubo & Kenya Tanaka. (2013) Fast breeder reactor core concept for heterogeneous minor actinide loading. Journal of Nuclear Science and Technology 50:1, pages 59-71.
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Articles from other publishers (6)
Yoshitaka Chikazawa, Atsushi Kato, Masatoshi Kameyama, Shoji Kotake, Shigenobu Kubo, Shigeo Ohki, Shuji Ohno, Kazuya Takano & Tomohiko Yamamoto. 2022. Sodium-cooled Fast Reactors. Sodium-cooled Fast Reactors
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Tomoyuki Uwaba, Masahiro Ito, Junichi Nemoto, Shoichi Ichikawa & Kozo Katsuyama. (2014) Verification of the FBR fuel bundle–duct interaction analysis code BAMBOO by the out-of-pile bundle compression test with large diameter pins. Journal of Nuclear Materials 452:1-3, pages 552-556.
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R. Ochoa, M. Vázquez, F. Álvarez-Velarde, F. Martín-Fuertes, N. García-Herranz & D. Cuervo. (2013) A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides. Annals of Nuclear Energy 57, pages 32-40.
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Tomoyuki Uwaba, Yasuhide Yano & Masahiro Ito. (2012) Resistance spot weldability of 11Cr–ferritic/martensitic steel sheets. Journal of Nuclear Materials 421:1-3, pages 132-139.
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H. Yamano, S. Kubo, Y. Shimakawa, K. Fujita, T. Suzuki & K. Kurisaka. (2012) Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor. Science and Technology of Nuclear Installations 2012, pages 1-14.
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Kosuke Tanaka, Masahiko Osaka, Shuhei Miwa, Takashi Hirosawa, Ken Kurosaki, Hiroaki Muta, Masayoshi Uno & Shinsuke Yamanaka. (2012) Preparation and characterization of the simulated burnup americium-containing uranium–plutonium mixed oxide fuel. Journal of Nuclear Materials 420:1-3, pages 207-212.
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