平成29年度 研究成果
論文
- 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
- International Journal of Hydrogen Energy, 42(19), p.13477 - 13485, 2017/05
- H. Q. Ho, Y. Honda, M. Goto, S. Takada
- Numerical investigation of the random arrangement effect of coated fuel particles on the criticality of HTTR fuel compact using MCNP6
- Annals of Nuclear Energy, 103, p.114 - 121, 2017/05
- H. 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, 2017/06
- M. Subekti, K. Kudo, K. Nabeshima, K. Takamatsu
- Determination of reactivity and neutron flux using modified neural network for HTGR
- Atom Indonesia, 43(2), p.93 - 102, 2017/08
- K. 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.
- O. Myagmarjav, N. Tanaka, M. Nomura, S. Kubo
- Hydrogen production tests by hydrogen iodide decomposition membrane reactor equipped with silica-based ceramics membrane
- International Journal of Hydrogen Energy, 42(49), p.29091 - 29100, 2017/12
- H. Noguchi, H. Takegami, S. Kasahara, N. Tanaka, Y. Kamiji, J. Iwatsuki, H. Aita, S. Kubo
- R&D status in thermochemical water-splitting hydrogen production iodine-sulfur process at JAEA
- Energy Procedia, 131, p.113 - 118, 2017/12
- Y. Fukaya, M. Goto, T. Nishihara
- Burn-up characteristics and criticality effect of impurities in the graphite structure of a commercial-scale prismatic HTGR
- Nuclear Engineering and Design, 326, p.108 - 113, 2018/01
- H. Q. Ho, Y. Honda, M. Goto, S. Takada
- Investigation of uncertainty caused by random arrangement of coated fuel particles in HTTR criticality calculations
- Annals of Nuclear Energy, 112, p.42 - 47, 2018/02
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/H2 plants
- 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/H2 test 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. Ohash
- 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.
- M. Goto, S. Ueta, J. Aihara, Y. Inaba, Y. Fukaya, Y. Tachibana, K. Okamoto
- Development of security and safety fuel for Pu-burner HTGR, 2; Design study of fuel and reactor core
- 25th International Conference on Nuclear Engineering (ICONE-25), Shanghai, China, July4-7, 2017.
- Y. Kamiji, K. Onuki, S. Kubo
- Corrosion resistance of nickel-based alloy to gaseous hydrogen iodide decomposition environment in thermochemical water-splitting iodine-sulfur process
- 5th International Conference on Chemical and Biological Sciences (ICCBS 2018), Bucharest, Romania, March 3-9,2018.
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 2017-02
- 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
- 広田 憲亮、岩月 仁、今井 良行、X. Yan
- 工業プロセスで生じる硫酸及びHI流体環境下における耐食性向上を目指したオーステナイト系Fe基合金及びNi基合金の開発方針
- JAEA-Technology 2017-027