Rchr
J-GLOBAL ID:202101005573336130   Update date: Oct. 01, 2022

Hamamoto Shimpei

ハマモト シンペイ | Hamamoto Shimpei
Affiliation and department:
Research theme for competitive and other funds  (1):
  • 核融合炉のためのトリチウム製造実証試験の検討とHTTR用リチウム装荷ロッドの設計
Papers (30):
  • Ho H. Q., Honda Yuki*, Hamamoto Shimpei, Ishii Toshiaki, Takada Shoji, Fujimoto Nozomu*, Ishitsuka Etsuo. Promising neutron irradiation applications at the high temperature engineering test reactor. Journal of Nuclear Engineering and Radiation Science. 2020. 6. 2. 021902\_1-021902\_6
  • Ho H. Q., Ishida Hiroki*, Hamamoto Shimpei, Ishii Toshiaki, Fujimoto Nozomu*, Takaki Naoyuki*, Ishitsuka Etsuo. Conceptual design of direct $^{\rm 99m}$Tc production facility at the high temperature engineering test reactor. Nuclear Engineering and Design. 2019. 352. 110174\_1-110174\_7
  • Ishii Toshiaki, Shimazaki Yosuke, Ono Masato, Fujiwara Yusuke, Ishitsuka Etsuo, Hamamoto Shimpei. Study on source of radioactive material in primary coolant of HTTR. Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive). 2018. 3
  • Ho H. Q., Honda Yuki*, Hamamoto Shimpei, Ishii Toshiaki, Takada Shoji, Fujimoto Nozomu*, Ishitsuka Etsuo. Feasibility study of new applications at the high-temperature gas-cooled reactor. Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive). 2018. 6
  • Ho H. Q., Honda Yuki*, Hamamoto Shimpei, Ishii Toshiaki, Fujimoto Nozomu*, Ishitsuka Etsuo. Feasibility study of large-scale production of iodine-125 at the high temperature engineering test reactor. Applied Radiation and Isotopes. 2018. 140. 209-214
more...
MISC (22):
  • Ishitsuka Etsuo, Nakashima Koki*, Nakagawa Naoki*, Ho H. Q., Ishii Toshiaki, Hamamoto Shimpei, Takamatsu Kuniyoshi, Kenzhina I.*, Chikhray Y.*, Matsuura Hideaki*, et al. Report of summer holiday practical training 2019; Feasibility study on nuclear battery using HTTR core; Feasibility study for nuclear design, 2. JAEA-Technology 2020-008. 2020. 16
  • Ishitsuka Etsuo, Matsunaka Kazuaki*, Ishida Hiroki*, Ho H. Q., Ishii Toshiaki, Hamamoto Shimpei, Takamatsu Kuniyoshi, Kenzhina I.*, Chikhray Y.*, Kondo Atsushi*, et al. Report of summer holiday practical training 2018; Feasibility study on nuclear battery using HTTR core; Feasibility study for nuclear design. JAEA-Technology 2019-008. 2019. 2019-008. 12
  • Nishihara Tetsuo, Yan X., Tachibana Yukio, Shibata Taiju, Ohashi Hirofumi, Kubo Shinji, Inaba Yoshitomo, Nakagawa Shigeaki, Goto Minoru, Ueta Shohei, et al. Excellent feature of Japanese HTGR technologies. JAEA-Technology 2018-004. 2018. 182
  • Hamamoto Shimpei, Sawahata Hiroaki, Suzuki Hisashi, Ishii Toshiaki, Yanagida Yoshinori. Development of temperature measurement technology for control rod using melt wire in High Temperature engineering Test Reactor (HTTR). JAEA-Technology 2017-012. 2017. 20
  • Shimazaki Yosuke, Ono Masato, Tochio Daisuke, Takada Shoji, Sawahata Hiroaki, Kawamoto Taiki, Hamamoto Shimpei, Shinohara Masanori. Development of transportation container for the neutron startup source of High Temperature engineering Test Reactor (HTTR). Proceedings of International Topical Meeting on Research Reactor Fuel Management and Meeting of the International Group on Reactor Research (RRFM/IGORR 2016) (Internet). 2016. 1034-1042
more...
Patents (1):
  • 一酸化炭素の酸化量制御による原子炉材料長寿命化の方法
Lectures and oral presentations  (37):
  • Evaluation of detailed neutron flux distribution in graphite moderated reactor by Monte Carlo code
    (日本原子力学会九州支部第39回研究発表講演会)
  • Study on T-production Li rod for high temperature gas cooled reactor; Temperature dependence of the hydrogen absorption speed in Zr
    (日本原子力学会2020年秋の大会)
  • Evaluation of power distribution of full core burnup calculation of the HTTR by Monte-Carlo method
    (日本原子力学会2020年秋の大会)
  • Evaluation of analysis accuracy in graphite-moderated reactor by Monte-Carlo code
    (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, 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)
more...
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