Furusawa Takayuki

フルサワタカユキ | Furusawa Takayuki

Affiliation and department：

Research field (1)： Nuclear engineering

Papers (18)：

Hamamoto Shimpei, Shimizu Atsushi, Inoi Hiroyuki, Tochio Daisuke, Homma Fumitaka, Sawahata Hiroaki, Sekita Kenji, Watanabe Shuji, Furusawa Takayuki, Iigaki Kazuhiko, et al. Improving the safety of the high temperature gas-cooled reactor "HTTR" based on Japan's new regulatory requirements. Nuclear Engineering and Design. 2022. 388. 111642\_1-111642\_11
Shimazaki Yosuke, Homma Fumitaka, Sawahata Hiroaki, Furusawa Takayuki, Kondo Masaaki. Development of the maintenance technologies for the future high-temperature gas cooled reactor (HTGR) using operating experiences acquired in high-temperature engineering test reactor (HTTR). Journal of Nuclear Science and Technology. 2014. 51. 11-12. 1413-1426
Shimizu Atsushi, Furusawa Takayuki, Homma Fumitaka, Inoi Hiroyuki, Umeda Masayuki, Kondo Masaaki, Isozaki Minoru, Fujimoto Nozomu, Iyoku Tatsuo. Operation and maintenance experience from the HTTR database. Journal of Nuclear Science and Technology. 2014. 51. 11-12. 1444-1451
Inaba Yoshitomo, Hamamoto Shimpei, Furusawa Takayuki, Saikusa Akio, Sakaba Nariaki. Investigation on dust captured by quintuple filters installed upstream of primary gas circulators in HTTR. Journal of Nuclear Science and Technology. 2014. 51. 11-12. 1373-1386
Shimizu Atsushi, Kawamoto Taiki, Tochio Daisuke, Saito Kenji, Sawahata Hiroaki, Homma Fumitaka, Furusawa Takayuki, Saikusa Akio, Takada Shoji, Shinozaki Masayuki. Development of operation and maintenance technology for HTGRs by using HTTR (High Temperature engineering Test Reactor). Nuclear Engineering and Design. 2014. 271. 499-504

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MISC (18)：

Nagasumi Satoru, Hasegawa Toshinari, Nakagawa Shigeaki, Kubo Shinji, Iigaki Kazuhiko, Shinohara Masanori, Saikusa Akio, Nojiri Naoki, Saito Kenji, Furusawa Takayuki, et al. Achievement of safety demonstration tests using HTTR; Loss of forced cooling test at 100\% reactor power (30 MW). JAEA-Research 2025-005. 2025. 23
Nemoto Takahiro, Fujiwara Yusuke, Arakawa Ryoki, Choyama Yuya, Nagasumi Satoru, Hasegawa Toshinari, Yokoyama Keisuke, Watanabe Masashi, Onishi Takashi, Kawamoto Taiki, et al. Differential pressure rise event for filters of HTTR primary helium gas circulators, 2; Investigation of filter deposits and recurrence prevention measures. JAEA-Technology 2024-003. 2024. 17
Nemoto Takahiro, Arakawa Ryoki, Kawakami Satoru, Nagasumi Satoru, Yokoyama Keisuke, Watanabe Masashi, Onishi Takashi, Kawamoto Taiki, Furusawa Takayuki, Inoi Hiroyuki, et al. Differential pressure rise event for filters of HTTR primary helium gas circulators, 1; Investigation of differential pressure rise event. JAEA-Technology 2023-005. 2023. 33
Nemoto Takahiro, Kaneshiro Noriyuki*, Sekita Kenji, Furusawa Takayuki, Kuroha Misao, Kawakami Satoru, Kondo Masaaki. Improvement in oil seal performance of gas compressor in HTTR, 2. JAEA-Technology 2015-006. 2015. 36
Goto Minoru, Takamatsu Kuniyoshi, Nakagawa Shigeaki, Ueta Shohei, Hamamoto Shimpei, Ohashi Hirofumi, Furusawa Takayuki, Saito Kenji, Shimazaki Yosuke, Nishihara Tetsuo. Preliminary study on HTTR tests for development of commercial HTGRs. JAEA-Technology 2009-053. 2009. 48

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Patents (1)：

加圧器

Lectures and oral presentations (5)：

Experience of the HTTR for workforce planning and staffing of small modular reactors
(Consultants' Meeting to develop the draft of the TECDOC on "Workforce Planning and Staffing of Small Modular Reactors")
Effort to pass review for checking conformity to new regulatory requirements for high temperature engineering test reactor, 1; Overview
(日本原子力学会2020年秋の大会)
Development of operation and maintenance technique with long term high temperature operation in HTTR, 2; Operation and maintenance of facilities and equipments unique for HTGRs
(平成22年度弥生研究会「研究炉等の運転・管理及び改良に関する研究会」)
Completion of long term high temperature operation of HTTR (High Temperature Engineering Test Reactor), 5; Operation and maintenance
(日本原子力学会2010年秋の大会)
Development of preservation technology for high temperature gas-cooled reactor
(日本保全学会第5回学術講演会)

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