Rchr
J-GLOBAL ID：202101012959284840
Update date: May. 01, 2024
Kamiyama Kenji
カミヤマ ケンジ | Kamiyama Kenji
Affiliation and department：
Research field (1)：
Nuclear engineering
Papers (81)：
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Imaizumi Yuya, Aoyagi Mitsuhiro, Kamiyama Kenji, Matsuba Kenichi, Akaev A.*, Mikisha A.*, Baklanov V.*, Vurim A.*. 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. 2023. 194. 110107\_1-110107\_11
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Zhang T.*, Yao Y.*, Morita Koji*, Liu X.*, Liu W.*, Imaizumi Yuya, Kamiyama Kenji. A Large-scale particle-based simulation of heat and mass transfer behavior in EAGLE ID1 in-pile test. Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet). 2023. 9
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Matsuba Kenichi, Emura Yuki, Kamiyama Kenji. A Series of molten stainless steel-sodium interaction experiments to develop an evaluation methodology for jet breakup during core disruptive accidents in sodium-cooled fast reactors. Proceedings of 2023 International Congress on Advanced in Nuclear Power Plants (ICAPP 2023) (Internet). 2023. 8
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Yamamoto Seishiro*, Odaira Naoya*, Ito Daisuke*, Ito Kei*, Saito Yasushi*, Imaizumi Yuya, Matsuba Kenichi, Kamiyama Kenji. Measurement of void fraction distribution in a sphere-packed bed using X-ray imaging. Konsoryu. 2023. 37. 1. 79-85
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Emura Yuki, Takai Toshihide, Kikuchi Shin, Kamiyama Kenji, Yamano Hidemasa, Yokoyama Hiroki*, Sakamoto Kan*. Thinning behavior of solid boron carbide immersed in molten stainless steel for core disruptive accident of sodium-cooled fast reactor. Journal of Nuclear Science and Technology. 2023. 10
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MISC (30)：
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Yamamoto Seishiro*, Odaira Naoya*, Ito Daisuke*, Ito Kei*, Saito Yasushi*, Imaizumi Yuya, Matsuba Kenichi, Kamiyama Kenji. Measurements of pressure drop and void fraction of air-water two-phase flow in a sphere-packed bed. Proceedings of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12) (Internet). 2022. 4
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Imaizumi Yuya, Aoyagi Mitsuhiro, Kamiyama Kenji, Matsuba Kenichi, Akayev A. S.*, Mikisha A. V.*, Baklanov V. V.*, Vurim A. D.*. Experiment and analysis for development of evaluation method for cooling of residual core materials in core disruptive accidents of sodium-cooled fast reactors. Dai-26-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet). 2022. 4
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Emura Yuki, Kamiyama Kenji, Yamano Hidemasa. Experimental study on reaction behavior between control rod material and molten stainless steel for core disruptive accidents of sodium-cooled fast reactors. Dai-26-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet). 2022. 4
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Kamiyama Kenji. The EAGLE Project to Enhance Safety of Sodium-Cooled Fast Reactor. Human Energy Atom. 2021. 2021. 2. 30-35
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Kamide Hideki, Sakamoto Yoshihiko, Kubo Shigenobu, Oki Shigeo, Ohshima Hiroyuki, Kamiyama Kenji. Progress of design and related researches of sodium-cooled fast reactor in Japan. Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive). 2017. 10
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Patents (2)：
Lectures and oral presentations (99)：
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Study on coolant behavior in damaged core of sodium-cooled fast reactor, 10; Evaluation of interfacial drag and observation of two-phase flow regime under negligibly small liquid flow rate condition
(日本原子力学会2024年春の年会)
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Experimental investigation on the heat transfer behavior of spherical particle bed with volumetric heating
(日本原子力学会九州支部第42回研究発表講演会)
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The Eagle project to enhance the safety of sodium-cooled fast reactors during the severe accidents
(X INTERNATIONAL CONFERENCE Semipalatinsk Test Site; Legacy and Prospects for Scientific- Technical Potential Development)
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Experimental studies in the EAGLE-3 project for controlled material relocation in severe accidents of sodium-cooled fast reactors
(X INTERNATIONAL CONFERENCE Semipalatinsk Test Site; Legacy and Prospects for Scientific- Technical Potential Development)
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Development of an evaluation method for in-place cooling of a degraded core in severe accidents of sodium-cooled fast reactors
(X INTERNATIONAL CONFERENCE Semipalatinsk Test Site; Legacy and Prospects for Scientific- Technical Potential Development)
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