Rchr
J-GLOBAL ID：202101003637405627
Update date: Oct. 27, 2025
Onoda Yuichi
オノダ ユウイチ | Onoda Yuichi
Affiliation and department：
Research field (1)：
Nuclear engineering
Papers (23)：
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Onoda Yuichi, Kubota Ryuzaburo*, Yamano Hidemasa. Core degradation behavior under ULOF transient on CFV-type core equipped SFR. Proceedings of 2025 International Congress on Advances in Nuclear Power Plants (ICAPP 2025) (Internet). 2025. 11
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Onoda Yuichi, Uchita Masato*, Tokizaki Minako*, Okazaki Hitoshi*. Detectability of pump/diagrid link rupture in pool-type sodium-cooled fast reactor. Nuclear Technology. 2025. 20
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Tobita Yoshiharu, Tagami Hirotaka, Ishida Shinya, Onoda Yuichi, Sogabe Joji, Okano Yasushi. Development of analysis methods for SFR severe accidents in JAEA and assessment of applicability to safety analysis. IAEA-TECDOC-2079. 2025. 72-84
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Hayakawa Satoshi*, Hagiwara Hiroyuki*, Imamura Akira*, Onoda Yuichi, Tanaka Masaaki, Nakamura Hironori*. Development of numerical evaluation method for heat transportation with sodium mist in the cover gas region of sodium-cooled fast reactor. Proceedings of 13th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS13) (Internet). 2024. 8
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Onoda Yuichi, Ishida Shinya, Fukano Yoshitaka, Kamiyama Kenji, Yamano Hidemasa, Kubo Shigenobu, Shibata Akihiro*, Bertrand F.*, Seiler N.*. France-Japan collaboration on severe accident studies in sodium-cooled fast reactors, 1; Severe accident scenarios assessment. Proceedings of International Conference on Nuclear Fuel Cycle (GLOBAL2024) (Internet). 2024. 4
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MISC (10)：
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Onoda Yuichi, Tobita Yoshiharu, Okano Yasushi. Analysis methodologies for the evaluation of ATWS accident on SFR in JAEA; Mechanical consequences during expansion phase of the accident. IAEA-TECDOC-2079. 2025. 215-225
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Sogabe Joji, Ishida Shinya, Tagami Hirotaka, Okano Yasushi, Kamiyama Kenji, Onoda Yuichi, Matsuba Kenichi, Yamano Hidemasa, Kubo Shigenobu, Kubota Ryuzaburo*, et al. France-Japan collaboration on severe accident studies in sodium-cooled fast reactors, 2; Methodologies and calculations of severe accident phases. Proceedings of International Conference on Nuclear Fuel Cycle (GLOBAL2024) (Internet). 2024. 4
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Onoda Yuichi, Yamano Hidemasa. Preliminary deformation analysis of the reactor vessel due to core debris accumulation onto the reactor vessel bottom for sodium-cooled fast reactor. Proceedings of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12) (Internet). 2022. 9
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Nakai Satoru, Aoyama Takafumi, Ito Chikara, Yamamoto Masaya, Iijima Minoru, Nagaoki Yoshihiro, Kobayashi Atsuko, Onoda Yuichi, Ohgama Kazuya, Uwaba Tomoyuki, et al. Celebration of 30th anniversary of the experimental fast reactor Joyo. Kosoku Jikkenro "Joyo" Rinkai 30-Shunen Kinen Hokokukai Oyobi Gijutsu Koenkai. 2008. 154
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Yamano Hidemasa, Onoda Yuichi, Tobita Yoshiharu, Sato Ikkenn. Interpretation of the CABRI-RAFT TPA2 Test. JNC TN9400 2005-045. 2005. 123
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Lectures and oral presentations (34)：
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Conceptual design for the sodium-cooled pool-type fast reactor, 9; Core safety evaluation for fuel selection (oxide fuel)
(日本原子力学会2025年秋の大会)
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International collaboration on severe accident studies for sodium-cooled fast reactor development in JAEA
(IAEA Technical Meeting on Advances and Innovations in Fast Reactor Design and Technology)
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Evaluation of core cooling characteristics during natural circulation operation in a sodium-cooled pool-type fast reactor
(日本原子力学会2025年秋の大会)
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The Effect of burn-up state on ULOF accident progression of Sodium-cooled Fast Reactor
(Joint IAEA-GIF Workshop on the Safety of Non-Water Cooled Reactors)
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Recriticality elimination by fuel discharge through controlled material relocation duct in an SFR
(Joint IAEA-GIF Workshop on the Safety of Non-Water Cooled Reactors)
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