Research field (3)：
Fluid engineering
, Nuclear engineering
, Thermal engineering
Research keywords (9)：
Concrete degradation
, Hydrogen explosion
, Volume of Fluid (VOF) method
, Multiphase flow
, Numelical simulation
, Lattice Gas Cellular Automata
, Vapor Explosion
, High Temperature Gas-cooled Reactor
, Thermal-hydraulics
Papers (41)：
Daisuke Tochio, Mitsuo Ozawa, Taku Koyama, Wataru Kikuchi. Consideration on the concrete spalling behavior in high-temperature environments during severe accidents. Journal of Nuclear Science and Technology. 2025. 1-6
Takeda, Tetsuaki, Inagaki, Yoshiyuki, Aihara, Jun, Aoki, Takeshi, Fujiwara, Yusuke, Fukaya, Yuji, Goto, Minoru, Ho, H. Q, Iigaki, Kazuhiko, Imai, Yoshiyuki, et al. High temperature gas-cooled reactors. JSME Series in Thermal and Nuclear Power Generation. 2021. 5. 1-464
Fujiwara Yusuke, Nemoto Takahiro, Tochio Daisuke, Shinohara Masanori, Ono Masato, Takada Shoji. Loss of core cooling test with one cooling line inactive in Vessel Cooling System of High-Temperature Engineering Test Reactor. Journal of Nuclear Engineering and Radiation Science. 2017. 3. 4. 041013\_1-041013\_8
Ono Masato, Fujiwara Yusuke, Honda Yuki, Sato Hiroyuki, Shimazaki Yosuke, Tochio Daisuke, Homma Fumitaka, Sawahata Hiroaki, Iigaki Kazuhiko, Takada Shoji. Measurement of temperature response of intermediate heat exchanger in heat application system abnormal simulating test using HTTR. Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM). 2017. 5
Honda Yuki, Tochio Daisuke, Nakagawa Shigeaki, Sekita Kenji, Homma Fumitaka, Sawahata Hiroaki, Sato Hiroyuki, Sakaba Nariaki, Takada Shoji. HTTR thermal load fluctuation test (non-nuclear heating test); Confirmation of HTGR system response against temperature transient. JAEA-Technology 2016-016. 2016. 16
Honda Yuki, Sato Hiroyuki, Nakagawa Shigeaki, Takada Shoji, Tochio Daisuke, Sakaba Nariaki, Sawa Kazuhiro. Validation of system analysis code with HTTR thermal load fluctuation test data (non-nuclear heating) and evaluation of reactor temperature behavior during upsets in hydrogen production plant. JAEA-Technology 2015-012. 2015. 17
Takada Shoji, Shinohara Masanori, Seki Tomokazu, Shimazaki Yosuke, Ono Masato, Tochio Daisuke, Iigaki Kazuhiko, Sawa Kazuhiro. Proposal of safety demonstration test plan of HTTR by cold test of loss of forced cooling with vessel cooling system inactive. JAEA-Technology 2014-001. 2014. 34
High Temperature Gas-cooled Reactors 1st Edition
Elsevier 2021
Lectures and oral presentations (27)：
Effort to pass review for checking conformity to new regulatory requirements for high temperature engineering test reactor, 4; Effects of graphite oxidation during the accidents that may release large amounts of radioactive materials
(日本原子力学会2020年秋の大会)
Effort to pass review for checking conformity to new regulatory requirements for high temperature engineering test reactor, 3; Reactor behavior and countermeasures during the accidents that may release large amounts of radioactive materials
(日本原子力学会2020年秋の大会)
Measurement of temperature response of intermediate heat exchanger in heat application system abnormal simulating test using HTTR
(Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM) 2017)
Effect of BP cell model for HTTR burnup characteristics
(日本原子力学会2016年秋の大会)
Characteristic confirmation test by using HTTR and investigation of absorbing thermal load fluctuation
(Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM) 2016)
