平成27年度 研究成果

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論文

K. Takamatsu
A Rapid evaluation method of the heat removed by a VCS before rise-to-power tests
Journal of Thermal Science, 24-3, (2015)295-301.
深谷裕司, 國富一彦, 小川益郎
高温ガス炉を用いた使用済み燃料の放射性潜在的有害度の低減に関する研究
日本原子力学会和文論文誌, 14-3, (2015)189-201.
Y. Fukaya, M. Goto, T. Nishihara
Study on erbium loading method to improve reactivity coefficients for low radiotoxic spent fuel HTGR
Nuclear Engineering and Design, 293, (2015)30-37
Dipu. A. L, H. Ohashi, S. Hamamoto, H. Sato, T. Nishihara
Assessment of amount and concentration of tritium in HTTR-IS system based on tritium behavior during high-temperature continuous operation of HTTR
Philippine Journal of Science, 88, (2016)126-134
Haneklaus. N, Reyes. R, Lim. W. G, Tabora. E.U, Palattao. B.L, Petrache. C, Vargas.E.P, K. Kunitomi, H. Ohashi, N. Sakaba, H. Sato, M. Goto, Yan. X, T. Nishihara, Tulsidas.H, Reitsma. F, Tarjan. S, Sathrugnan. K, Jacimovic. R, Khaledi. N, Birky. B. K, Schnug. E
Energy neutral phosphate fertilizer production using high temperature reactors; A Philippine case study
Philippine Journal of Science, 144-1,(2015)69-7
Y. Kawamoto, H. Nakaya, H. Matsuura, K. Katayama, M. Goto, S. Nakagawa
Study on operation scenario of tritium production for a fusion reactor using a high temperature gas-cooled reactor
Fusion Science and Technology, 68-2(2015)397-401

国際会議

H. Sato, J. Sumita, A. Terada, H. Ohashi, Yan. X, T. Nishihara, Y. Tachibana, Y. Inagaki
HTTR demonstration program for nuclear cogeneration of hydrogen and electricity
23rd International Conference on Nuclear Engineering (ICONE-23), Chiba, Japan, May17-21, 2015
S. Kasahara, T. Murata, Y. Kamiji, A. Terada, Yan. X, Y. Inagaki, M. Mori
Heat transport analysis in a district heating and snow melting system in Sapporo and Ishikari, Hokkaido applying waste heat from GTHTR300
23rd International Conference on Nuclear Engineering (ICONE-23), Chiba, Japan, May17-21, 2015
H. Sato, H. Ohashi, S. Nakagawa, Y. Tachibana, K. Kunitomi
Safety design consideration for HTGR coupling with hydrogen production plant
4th International Symposium on Innovative Nuclear Energy Systems (INES-4), Tokyo, Japan, November6-8, 2013
M. Goto, K. Demachi, S. Ueta, M. Nakano, M. Honda, Y. Tachibana, Y. Inaba, J. Aihara, Y. Fukaya, N. Tsuji, M. Takahashi, Y. Saiki, K. Hayato, K. Kunitomi, K. Ohashi, K. Kitagawa, K. Okamoto
Conceptual study of a plutonium burner high temperature gas-cooled reactor with high nuclear proliferation resistance
21st International Conference \& Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015), Paris, France, September20-24, 2015
H. Sato, Yan. X, J. Sumita, A. Terada, T. Nishihara,
Automated control for electric-thermal load following operation in nuclear gas turbine cogeneration system
International Gas Turbine Congress 2015 (IGTC 2015), Tokyo, Japan, November15-20, 2015
I. Ioka, Y. Kuriki, J. Iwatsuki, S. Kubo, Y. Inagaki
Development research of corrosion-resistant structural material using Fe-Si alloy lining centrifugal cast-iron for thermochemical water-splitting iodine-sulfur process
23rd International Conference on Nuclear Engineering (ICONE-23), Chiba, Japan, May17-21, 2015

公開報告書等

立松研二, 松本裕之
平成26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水素製造技術の研究開発」
JAEA-Evaluation 2015-001
野本恭信, 相原純, 中川繁昭, 井坂和義, 大橋弘史
ピン・イン・ブロック型高温ガス炉の燃料棒からの事故時核分裂生成物追加放出量計算コードHTFP
JAEA-Data/Code 2015-008
深谷裕司, 後藤実, 西原哲夫
潜在的有害度の発生を抑える新型高温ガス炉の研究
JAEA-Research 2015-023
深谷裕司, 後藤実, 西原哲夫
クリーンバーン高温ガス炉詳細設計のための核設計モデルの整備
JAEA-Technology 2015-017
相原純, 植田祥平, 西原哲夫
FORNAX-Aの応用
JAEA-Technology 2015-040
Y. Inaba, Lee. T, S. Ueta, S. Kasahara, Y. Honda, Lee. H, Kim. E, Cho. M, Bae. K, N. Sakaba
Proceedings of 7th KAERI-JAEA Information Exchange Meeting on HTGR and Nuclear Hydrogen Technology; November 5th-6th, 2015, JAEA Oarai Research and Development Center, Oarai, Japan
JAEA-Review 2015-043
久保真治, 岩月仁, 竹上弘彰, 笠原清司, 田中伸幸, 野口弘喜, 上地優, 小貫薫
熱化学水素製造法ISプロセスの実用材料製反応機器およびヨウ化水素濃縮技術に関する研究開発
JAEA-Technology 2015-028