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Journal of Nuclear Science and Technology Volume 48, 2011 - Issue 2
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ARTICLE

Three-Pin Cluster CABRI Tests Simulating the Unprotected Loss-of-Flow Accident in Sodium-Cooled Fast Reactors

Yuichi ONODA Japan Atomic Energy Agency, 4002 Narita-cho, O-arai-machi, Higashi-Ibaraki-gun, Ibaraki, 311-1393, Japan
,
Yoshitaka FUKANO Japan Atomic Energy Agency, 4002 Narita-cho, O-arai-machi, Higashi-Ibaraki-gun, Ibaraki, 311-1393, Japan
,
Ikken SATO Japan Atomic Energy Agency, 4002 Narita-cho, O-arai-machi, Higashi-Ibaraki-gun, Ibaraki, 311-1393, Japan
,
Christophe MARQUIE Institut de Radioprotection et de Sûreté Nucléaire, 13108, St. Paul lez Durance Cedex, France
&
Bertrand DUC Commissariat à l'Energie Atomique, 13108, St. Paul lez Durance Cedex, France
Pages 188-204 | Received 31 Aug 2009, Accepted 16 Jul 2010, Published online: 05 Jan 2012

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Kenji Kamiyama, Kensuke Konishi, Ikken Sato, Jun-ichi Toyooka, Ken-ichi Matsuba, Vladimir A. Zuyev, Alexander V. Pakhnits, Vladimir A. Vityuk, Alexander D. Vurim, Valery A. Gaidaichuk, Alexander A. Kolodeshnikov & Yuri S. Vassiliev. (2014) Experimental studies on the upward fuel discharge for elimination of severe recriticality during core-disruptive accidents in sodium-cooled fast reactors. Journal of Nuclear Science and Technology 51:9, pages 1114-1124.
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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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Kenji Kamiyama, Masaki Saito, Ken-ichi Matsuba, Mikio Isozaki, Ikken Sato, Kensuke Konishi, VradimirA. Zuyev, AlexanderA. Kolodeshnikov & YuriS. Vassiliev. (2013) Experimental study on fuel-discharge behaviour through in-core coolant channels. Journal of Nuclear Science and Technology 50:6, pages 629-644.
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Articles from other publishers (7)

Hideki Kamide, Hiroyuki Ohshima, Shigenobu Kubo & Yoshitaka Chikazawa. 2023. Handbook of Generation IV Nuclear Reactors. Handbook of Generation IV Nuclear Reactors 395 418 .
Kosuke Aizawa, Masanori Ando, Yoshitaka Chikazawa, Norihiro Doda, Yasuhiro Enuma, Toshiki Ezure, Yoshitaka Fukano, Erina Hamase, Shun Hirooka, Tomoyuki Hiyama, Katsunori Ishii, Takeji Kaito, Kenji Kamiyama, Norihiro Kikuchi, Jun Kobayashi, Shigenobu Kubo, Akikazu Kurihara, Shuhei Maruyama, Kentaro Matsushita, Takero Mori, Koji Morita, Hiroaki Ohira, Shigeo Ohki, Satoshi Okajima, Yasushi Okano, Takashi Onizawa, Ayako Ono, Takayuki Ozawa, Hiroshi Seino, Takashi Takata, Shigeru Takaya, Masayuki Takeuchi, Masaaki Tanaka, Hiroshi Taninaka, Takashi Tanno, Kodai Toyota, Akihiro Uchibori, Tomoyuki Uwaba, Takashi Wakai, Tomoyoshi Watakabe, Hiroki Yada, Tomohiko Yamamoto, Hidemasa Yamano, Kenji Yokoyama, Ryuji Yoshikawa, Kazuo Yoshimura, Ryuta Hashidate, Yuichi Sano & Akiyuki Seki. 2022. Sodium-cooled Fast Reactors. Sodium-cooled Fast Reactors 409 626 .
Prasant Kumar Panigrahi & K. Velusamy. (2021) Thermal-hydraulic analysis of FAIDUS design for severe accident mitigation strategy in a medium size sodium-cooled fast reactor. Nuclear Engineering and Design 379, pages 111222.
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Prasant Kumar Panigrahi & K. Velusamy. (2019) A robust multi phase model to investigate molten material relocation during total flow blockage in SFR fuel subassembly. Annals of Nuclear Energy 133, pages 59-72.
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H. Kamide, H. Ohshima, T. Sakai & M. Morishita. 2016. Handbook of Generation IV Nuclear Reactors. Handbook of Generation IV Nuclear Reactors 283 307 .
Yoshitaka Fukano. (2015) SAS4A analysis on hypothetical total instantaneous flow blockage in SFRs based on in-pile experiments. Annals of Nuclear Energy 77, pages 376-392.
Crossref
Ken-ichi Matsuba, Mikio Isozaki, Kenji Kamiyama & Yoshiharu Tobita. (2013) Mechanism of Upward Fuel Discharge During Core Disruptive Accidents in Sodium-Cooled Fast Reactors. Journal of Engineering for Gas Turbines and Power 135:3.
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