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Shinya Ishida, Yoshitaka Fukano, Yoshiharu Tobita & Yasushi Okano. (2023) Numerical study of initiating phase of core disruptive accident in small sodium-cooled fast reactors with negative void reactivity. Journal of Nuclear Science and Technology 0:0, pages 1-13.
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Ken-ichi Kawada & Tohru Suzuki. (2021) Study on dominant aspects of unprotected loss-of-flow to be evaluated in the initiating phase for a sodium-cooled fast reactor. Journal of Nuclear Science and Technology 58:3, pages 347-360.
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Tohru Suzuki, Kenji Kamiyama, Hidemasa Yamano, Shigenobu Kubo, Yoshiharu Tobita, Ryodai Nakai & Kazuya Koyama. (2014) A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention. Journal of Nuclear Science and Technology 51:4, pages 493-513.
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Ikken SATO, Yoshiharu TOBITA, Kensuke KONISHI, Kenji KAMIYAMA, Jun-ichi TOYOOKA, Ryodai NAKAI, Shigenobu KUBO, Shoji KOTAKE, Kazuya KOYAMA, Yuri VASSILIEV, Alexander VURIM, Vladimir ZUEV & Alexander KOLODESHNIKOV. (2011) Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident. Journal of Nuclear Science and Technology 48:4, pages 556-566.
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Yuichi ONODA, Yoshitaka FUKANO, Ikken SATO, Christophe MARQUIE & Bertrand DUC. (2011) Three-Pin Cluster CABRI Tests Simulating the Unprotected Loss-of-Flow Accident in Sodium-Cooled Fast Reactors. Journal of Nuclear Science and Technology 48:2, pages 188-204.
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Yoshitaka FUKANO, Yuichi ONODA & Ikken SATO. (2010) Fuel Pin Behavior up to Cladding Failure under Pulse-Type Transient Overpower in the CABRI-FAST and CABRI-RAFT Experiments. Journal of Nuclear Science and Technology 47:4, pages 396-410.
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Yoshitaka FUKANO, Yuichi ONODA, Ikken SATO & Jean CHARPENEL. (2009) Fuel Pin Behavior under Slow-Ramp-type Transient-Overpower Conditions in the CABRI-FAST Experiments. Journal of Nuclear Science and Technology 46:11, pages 1049-1058.
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Philippe Martin, Michel Pelletier, Denis Every & Derek Buckthorpe. (2008) French and United Kingdom Experience of High-Burnup Mixed-Oxide Fuel in Sodium-Cooled Fast Breeder Reactors. Nuclear Technology 161:1, pages 35-44.
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