Research keywords (4)：
severe accident
, reactivity estimation
, criticality accident
, criticality safety
Research theme for competitive and other funds (1)：
2018 - 東京電力福島第一原子力発電所 燃料デブリの臨界評価手法の整備
Papers (56)：
Fukuda Kodai, Yamane Yuichi. Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system. Journal of Nuclear Science and Technology. 2023. 60. 12. 1514-1525
Suyama Kenya, Ueki Taro, Gunji Satoshi, Watanabe Tomoaki, Araki Shohei, Fukuda Kodai, Yamane Yuichi, Izawa Kazuhiko, Nagaya Yasunobu, Kikuchi Takeo, et al. Study on criticality safety control of fuel debris for validation of methodology applied to the safety regulation. Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet). 2023. 6
Fukuda Kodai, Yamane Yuichi. Multiphysics analysis of reactivity changes due to solution flow in the past criticality accident at Windscale Works in 1970. Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet). 2023. 9
Watanabe Tomoaki, Yamane Yuichi. Power profile analysis of criticality accidents involving fissile solution boiling with considering evaporation. Journal of Nuclear Science and Technology. 2023. 9
Yamane Yuichi. Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state. Journal of Nuclear Science and Technology. 2022. 59. 11. 1331-1344
Okuno Hiroshi, Suyama Kenya, Tonoike Kotaro, Yamane Yuichi, Yamamoto Toshihiro, Miyoshi Yoshinori, Uchiyama Gunzo. Second version of data collection part of nuclear criticality safety handbook (Contract research). JAEA-Data/Code 2009-010. 2009. 175
Yoshida Kazuo, Abe Hitoshi, Yamane Yuichi, Tashiro Shinsuke, Muramatsu Ken. Research on the state-of-the-art of accident consequence analysis method for non-reactor nuclear facilities, 1. JAEA-Research 2007-047. 2007. 70
Kinetics analysis to investigate effects of fuel debris particle size on criticality behavior in terms of thermal transfer
(日本原子力学会2023年春の年会)
Development of PIRT for boiling and drying out accident analysis at fuel reprocessing plant, 1; Positioning of development of PIRT for boiling and drying out accident analysis
(日本原子力学会2023年春の年会)
The Estimation of the power profile and reactivity by using cubic spline interpolation
(日本原子力学会2023年春の年会)
Reactivity estimation of UTR-KINKI subcritical cores; Estimation based on power profile in quasi-steady state
(日本原子力学会2022年春の年会)
Analysis of criticality incident at Windscale Works
(京都大学複合原子力科学研究所第9回炉物理専門研究会)
2016/03 - Atomic Energy Society of Japan JNST Most Popular Article Award 2016 Improvement in estimation of maximum first peak power based on non-linear temperature feedback reactivity in criticality accident with instantaneous reactivity insertion
2010/10 - Japan Atomic Energy Agency research development achievement award
Association Membership(s) (2)：
THE PHYSICAL SOCIETY OF JAPAN
, ATOMIC ENERGY SOCIETY OF JAPAN
