国立研究開発法人日本原子力研究開発機構
高温ガス炉水素・熱利用研究センター

国立研究開発法人日本原子力研究開発機構
高温ガス炉水素・熱利用研究センター

平成29年度

  • 論文
  • 国際会議
  • 公開報告書等

論文

  • T. TAKAMATSU
    Thermal-hydraulic analyses of the High-Temperature engineering Test Reactor for loss of forced cooling at 30% reactor power
    Annals of Nuclear Energy,106,(2017)71-83.
  • S. Sato, H. Ohashi, S. Nakagawa
    Design approach for mitigation of air ingress in high temperature gas-cooled reactor
    Mechanical Engineering Journal (Internet), 4-3, (2017)16-495_1-16-495_11.

国際会議

  • Y. Honda, H. Sato, H. Ohashi
    Probabilistic risk assessment method development for high temperature gas-cooled reactor, 5; Accident progression analysis
    2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017), Fukui/Kyoto, Japan, April24-28, 2017.
  • Y. Nomoto, S. Horii, J. Sumita, H. Sato, X. Yan
    Cost performance design for high temperature helium heat transport piping of GTHTR300C and HTTR-GT/H2plants
    2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017), Fukui/Kyoto, Japan, April24-28, 2017.
  • H. Sato, A. Nishida, H. Ohashi, K. Muramatsu, H. Muta, T. Itoi, T. Takada, T. Hida, M. Tanabe, T. Yamamoto, H. Shimada, T. Ikeda
    Probabilistic risk assessment method development for high temperature gas-cooled reactors, 1; Project overviews
    2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017), Fukui/Kyoto, Japan, April24-28, 2017.
  • K. Matsuda, K. Muramatsu, H. Muta, H. Sato, A. Nishida, H. Ohashi, T. Itoi, T. Takada, T. Hida, M. Tanabe, T. Yamamoto, H. Shimada, T. Ikeda
    Probabilistic risk assessment method development for high temperature gas-cooled reactors, 2; Development of accident sequence analysis methodology
    2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017), Fukui/Kyoto, Japan, April24-28, 2017.
  • S. Kasahara, J. Iwatsuki, H. Takegami, N. Tanaka, H. Noguchi, Y. Kamiji, K. Onuki, S. Kubo
    Current R&D status of thermochemical water splitting iodine-sulfur process in Japan Atomic Energy Agency
    21st World Hydrogen Energy Conference (WHEC 2016), Zaragoza, Spain, June13-16, 2016.
  • H. Nakaya, H. Matsuura, K. Katayama, M. Goto, S. Nakagawa
    Application of the high-temperature gas-cooled reactor to produce tritium for fusion reactors
    2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, France, May3-6, 2015.
  • X. Yan, H. Sato, J. Sumita, Y. Nomoto, S. Horii, Y. Imai, S. Kasahara, K. Suzuki, J. Iwatsuki, A. Terada, Y. Tachibana, M. Ono, S. Yamada, K. Suyama
    HTTR-GT/H 2test plant; System design
    8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.
  • Y. Honda, H. Sato, S. Nakagawa, H. Ohashi
    Uncertainty analysis for source term evaluation of high temperature gas-cooled reactor under accident conditions; Identification of influencing factors in loss-of-forced circulation accidents
    25th International Conference on Nuclear Engineering (ICONE-25), Shanghai, China, July4-7, 2017.
  • S. Ueta, J. Aihara, M. Goto, Y. Tachibana, K. Okamoto
    Development of security and safety fuel for Pu-burner HTGR, 5; Test and characterization for ZrC coating
    25th International Conference on Nuclear Engineering (ICONE-25), Shanghai, China, July4-7, 2017.

公開報告書等

  • 今井良行, 佐藤博之, X.Yan
    高温ガス炉に接続するヘリウムガスタービンの設計データ(改訂版)
    JAEA-Data/Code 2017-011
  • 佐藤博之, X.Yan, 大橋弘史
    HTTR接続熱利用システムのプラント過渡挙動評価;ヘリウムガスタービンと水素製造施設接続に伴うHTTRの安全評価
    JAEA-Technology 2017-020
  • 立松研二, 西原哲夫
    平成28年度研究開発・評価報告書; 評価課題「高温ガス炉とこれによる熱利用技術の研究開発」(中間評価)
    JAEA-Evaluation 2017-001
  • 中川繁昭, 佐藤博之, 深谷裕司, 徳原一実, 大橋弘史
    実用高温ガス炉の安全要件を達成するための燃料・炉心の設計事項
    JAEA-Technology 2017-022
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