Search Results - "Furusawa, Takayuki"

  • Showing 1 - 12 results of 12
Refine Results
  1. 1
  2. 2

    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) by Shimazaki, Yosuke, Homma, Fumitaka, Sawahata, Hiroaki, Furusawa, Takayuki, Kondo, Masaaki

    Published in Journal of nuclear science and technology (02-12-2014)
    “…This paper describes the lessons learned of the maintenance technologies, which have been and will be developed by using the high-temperature engineering test…”
    Get full text
    Journal Article
  3. 3

    Investigation on dust captured by quintuple filters installed upstream of primary gas circulators in HTTR by Inaba, Yoshitomo, Hamamoto, Shimpei, Furusawa, Takayuki, Saikusa, Akio, Sakaba, Nariaki

    Published in Journal of nuclear science and technology (02-12-2014)
    “…A main objective to install filters upstream of primary gas circulators in the high temperature engineering test reactor (HTTR), besides having a primary…”
    Get full text
    Journal Article
  4. 4

    Investigation of chemical characteristics of primary helium gas coolant of HTTR (high temperature engineering test reactor) by Hamamoto, Shimpei, Shimazaki, Yosuke, Furusawa, Takayuki, Nemoto, Takahiro, Inoi, Hiroyuki, Takada, Shoji

    Published in Nuclear engineering and design (01-05-2014)
    “…The technical basis of helium gas purification control for HTGRs was established by verifying the design of the Primary Helium Purification System (PHPS) of…”
    Get full text
    Journal Article
  5. 5

    Operation and maintenance experience from the HTTR database by Shimizu, Atsushi, Furusawa, Takayuki, Homma, Fumitaka, Inoi, Hiroyuki, Umeda, Masayuki, Kondo, Masaaki, Isozaki, Minoru, Fujimoto, Nozomu, Iyoku, Tatsuo

    Published in Journal of nuclear science and technology (02-12-2014)
    “…The Japan Atomic Energy Agency has been establishing a database of operation and maintenance experience for the High Temperature Engineering Test Reactor. The…”
    Get full text
    Journal Article
  6. 6

    Development of operation and maintenance technology for HTGRs by using HTTR (High Temperature engineering Test Reactor) by Shimizu, Atsushi, Kawamoto, Taiki, Tochio, Daisuke, Saito, Kenji, Sawahata, Hiroaki, Honma, Fumitaka, Furusawa, Takayuki, Saikusa, Akio, Takada, Shoji, Shinozaki, Masayuki

    Published in Nuclear engineering and design (01-05-2014)
    “…To establish the technical basis of HTGR (High Temperature Gas cooled Reactor), the long term high temperature operation using HTTR was carried out in the high…”
    Get full text
    Journal Article
  7. 7

    Short design descriptions of other systems of the HTTR by Sakaba, Nariaki, Furusawa, Takayuki, Kawamoto, Taiki, Ishii, Yoshiki, Oota, Yukimaru

    Published in Nuclear engineering and design (01-10-2004)
    “…The HTTR mainly consists of the core components, reactor pressure vessel, cooling systems, instrumentation and control systems, and containment structures. The…”
    Get full text
    Journal Article
  8. 8

    Cooling system design and structural integrity evaluation by Furusawa, Takayuki, Shinozaki, Masayuki, Hamamoto, Shimpei, Oota, Yukimaru

    Published in Nuclear engineering and design (01-10-2004)
    “…The high temperature engineering test reactor (HTTR), which is the first high temperature gas-cooled reactor (HTGR) in Japan, is a test reactor with a thermal…”
    Get full text
    Journal Article
  9. 9
  10. 10
  11. 11

    Plan for first phase of safety demonstration tests of the High Temperature Engineering Test Reactor (HTTR) by Tachibana, Yukio, Nakagawa, Shigeaki, Takeda, Takeshi, Saikusa, Akio, Furusawa, Takayuki, Takamatsu, Kuniyoshi, Sawa, Kazuhiro, Iyoku, Tatsuo

    Published in Nuclear engineering and design (01-09-2003)
    “…Safety demonstration tests using the High Temperature Engineering Test Reactor (HTTR) will be conducted for the purpose of demonstrating inherent safety…”
    Get full text
    Journal Article
  12. 12

    Inspection techniques for primary pressurized water cooler tubes in the high temperature engineering test reactor by Takeda, Takeshi, Furusawa, Takayuki, Shinozaki, Masayuki, Miyamoto, Satoshi

    Published in Nuclear engineering and design (01-08-2002)
    “…A primary pressurized water cooler (PPWC) with 136 inverse-U-tubes is installed in the primary cooling system of the high temperature engineering test reactor…”
    Get full text
    Journal Article