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J-GLOBAL ID:202101002204661053   Update date: May. 13, 2024

Nakagawa Shigeaki

ナカガワ シゲアキ | Nakagawa Shigeaki
Affiliation and department:
Research field  (1): Nuclear engineering
Research theme for competitive and other funds  (5):
  • 2021 - 2024 Design and production of tritium production test modules for irradiation test using High Temperature engineering Test Reactor
  • 2015 - 2018 Development of Li-loading rod of high-temperature gas-cooled reactor for tritium production
  • 2014 - 2018 A study on a high temperature gas-cooled reactor as a tritium production device for fusion reactors
  • 2013 - 2015 Development of effective lithium loading method into high-temperature gas-cooled reactor for tritium poroduction
  • 2011 - 2012 Study on tritium production for fusion reactors using high-temperature gas-cooled reactor
Papers (78):
  • Fukaya Yuji, Okita Shoichiro, Nakagawa Shigeaki, Goto Minoru, Ohashi Hirofumi. Computed tomography neutron detector system to observe power distribution in a core with long neutron flight path. Annals of Nuclear Energy. 2022. 168. 108911\_1-108911\_7
  • Hamamoto Shimpei, Ishitsuka Etsuo, Nakagawa Shigeaki, Goto Minoru, Matsuura Hideaki*, Katayama Kazunari*, Otsuka Teppei*, Tobita Kenji*. Study on chemical form of tritium in coolant helium of high temperature gas-cooled reactor with tritium production device. Proceedings of 2021 International Congress on Advances in Nuclear Power Plants (ICAPP 2021) (USB Flash Drive). 2021. 5
  • Fukaya Yuji, Goto Minoru, Nakagawa Shigeaki, Nakajima Kunihiro*, Takahashi Kazuki*, Sakon Atsushi*, Sano Tadafumi*, Hashimoto Kengo*. Reactor physics experiment in a graphite-moderation system for HTGR. Proceedings of International Conference on the Physics of Reactors; Transition To A Scalable Nuclear Future (PHYSOR 2020) (USB Flash Drive). 2020. 8
  • Goto Minoru, Okumura Keisuke, Nakagawa Shigeaki, Inaba Yoshitomo, Matsuura Hideaki*, Nakaya Hiroyuki*, Katayama Kazunari*. Nuclear and thermal feasibility of lithium-loaded high temperature gas-cooled reactor for tritium production for fusion reactors. Fusion Engineering and Design. 2018. 136. Part A. 357-361
  • Takada Shoji, Honda Yuki*, Inaba Yoshitomo, Sekita Kenji, Nemoto Takahiro, Tochio Daisuke, Ishii Toshiaki, Sato Hiroyuki, Nakagawa Shigeaki, Sawa Kazuhiro*. Numerical evaluation on fluctuation absorption characteristics based on nuclear heat supply fluctuation test using HTTR. Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive). 2018. 7
more...
MISC (85):
  • 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. High Temperature Gas-Cooled Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.5. 2021. 464
  • Fukaya Yuji, Goto Minoru, Nakagawa Shigeaki. Recent R\&D of HTGR and requirement for nuclear data. JAEA-Conf 2020-001. 2020. 27-32
  • Fukaya Yuji, Nakagawa Shigeaki, Goto Minoru, Ishitsuka Etsuo, Kawakami Satoru, Uesaka Takahiro, Morita Keisuke, Sano Tadafumi*. Reactor physics experiment in graphite moderation system for HTGR, 1. KURNS Progress Report 2018. 2019. 148
  • 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
  • Nakagawa Shigeaki, Sato Hiroyuki, Fukaya Yuji, Tokuhara Kazumi, Ohashi Hirofumi. Evaluation items to attain safety requirements in fuel and core designs for commercial HTGRs. JAEA-Technology 2017-022. 2017. 32
more...
Patents (4):
  • METHOD AND APPARATUS FOR MEASURING A POWER DISTRIBUTION IN A REACTOR CORE
  • 原子炉内出力分布の測定方法及びその装置
  • 原子炉内出力分布の測定方法及びその装置
  • 原子炉内出力分布の測定方法及びその装置
Lectures and oral presentations  (61):
  • Study on tritium production using high-temperature gas-cooled reactor for fusion reactors; Structure of the irradiation test module and experimental method
    (日本原子力学会2023年秋の大会)
  • Study on T production using high-temperature gas-cooled reactor for fusion reactors, 4; Feasibility study on irradiation test for tritium production capsule
    (日本原子力学会2023年春の年会)
  • 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)
  • Li nuclear heat generation in the HTGR for T production and effect on T containment performance
    (第36回プラズマ・核融合学会年会)
  • R\&D to improve accuracy of nuclear prediction for HTGR, 1; Experiment of first mock-up reactor with graphite system in KUCA
    (日本原子力学会2019年春の年会)
more...
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