Hideki Kamide, Tai Asayama, Takashi Wakai, Toshiki Ezure, Akihiro Uchibori, Shigenobu Kubo & Masayuki Takeuchi. (2024) Progress of sodium-cooled fast reactor developments in Japan taking into account total lifecycle, risk-informed approach, and sustainability. Nuclear Engineering and Design 421, pages 113062.
Crossref
Yuya Imaizumi, Mitsuhiro Aoyagi, Kenji Kamiyama, Ken-ichi Matsuba, Assan Akaev, Anatoly Mikisha, Viktor Baklanov & Alexandr Vurim. (2023) Experiment and new analysis model simulating in-place cooling of a degraded core in severe accidents of sodium-cooled fast reactors. Annals of Nuclear Energy 194, pages 110107.
Crossref
Erlan Batyrbekov, Vladimir Vityuk, Alexander Vurim & Galina Vityuk. (2023) Experimental opportunities and main results of the impulse graphite reactor use for research in safety area. Annals of Nuclear Energy 182, pages 109582.
Crossref
Ting Zhang, Koji Morita, Xiaoxing Liu, Wei Liu & Kenji Kamiyama. (2022) A 3D particle-based simulation of heat and mass transfer behavior in the EAGLE ID1 in-pile test. Annals of Nuclear Energy 179, pages 109389.
Crossref
G. A. Vityuk, V. A. Vityuk, A. D. Vurim, M. K. Skakov & A. V. Gradoboyev. (2022) Feasibility study mixed oxide fuel tests in the impulse graphite reactor. Eurasian Journal of Physics and Functional Materials 6:3, pages 198-212.
Crossref
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
.
Eszter Csengeri, Andrea Bachrata, Laurent Trotignon & Elsa Merle. (2021) Comparative Study of Physical Models for Particle Sedimentation Using SIMMER Code. Journal of Nuclear Engineering and Radiation Science 7:4.
Crossref
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.
Crossref
Ting Zhang, Kanji Funakoshi, Xiaoxing Liu, Wei Liu, Koji Morita & Kenji Kamiyama. (2021) Numerical simulation of heat transfer behavior in EAGLE ID1 in-pile test using finite volume particle method. Annals of Nuclear Energy 150, pages 107856.
Crossref
Galina Vityuk, Alexander Vurim, Mazhyn Skakov & Alexander Pakhnits. (2021) Methods and results of determining the impurity gas amount in ceramic fuel. Annals of Nuclear Energy 150, pages 107843.
Crossref
Vladimir Vityuk & Alexander Vurim. (2019) Method for determining the energy parameters in pulse reactor experiments. Annals of Nuclear Energy 127, pages 196-203.
Crossref
Keiko Chitose, Hiroyasu Mochizuki & Naoyuki Takaki. (2017) Thermal-hydraulic Feasibility Study of a Convex shaped Fast Reactor Core. Energy Procedia 131, pages 86-93.
Crossref
V. A. Vityuk, A. D. Vurim, V. M. Kotov & A. V. Pakhnits. (2016) Determination of the Parameters for Fuel Assembly Tests in a Pulsed Graphite Reactor. Atomic Energy 120:5, pages 323-327.
Crossref
Ken-ichi MATSUBA, Kenji KAMIYAMA, Jun-ichi TOYOOKA, Yoshiharu TOBITA, Vladimir A. ZUYEV, Alexander A. KOLODESHNIKOV & Yuri S. VASSILIEV. (2016) Experimental discussion on fragmentation mechanism of molten oxide discharged into a sodium pool. Mechanical Engineering Journal 3:3, pages 15-00595-15-00595.
Crossref
Erlan Batyrbekov, Vladimir Vityuk, Alexander Vurim & Galina Vityuk. (2022) Experimental Opportunities and Main Results of the Impulse Graphite Reactor Use for Research in Safety Area. SSRN Electronic Journal.
Crossref