令和元年度(平成31年度) 研究成果

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  2. 研究成果
  3. 令和元年度(平成31年度)

論文

Y. Fukaya, M. Goto, S. Nakagawa, K. Nakajima, K. Takahashi, A. Sakon, T. Sano, K. Hashimoto
Reactor physics experiment in a graphite-moderation system for HTGR
Proceedings of International Conference on the Physics of Reactors; Transition To A Scalable Nuclear Future (PHYSOR 2020) (USB Flash Drive), 8 Pages, 2020/03
S. Ueta, N. Mizuta, Y. Fukaya, M. Goto, Y. Tachibana, M. Honda, Y. Saiki, M. Takahashi, K. Ohira, M. Nakano, K. Ohashi, K. Okamoto
Study on plutonium burner high temperature gas-cooled reactor in Japan – Introduction scenario, reactor safety and fabrication tests of the 3S-TRISO fuel
Nuclear Engineering and Design, 357, p.110419_1 - 110419_10, 2020/02
K. Takamatsu, T. Matsumoto, W. Liu, K. Morita
Comparative methodology between actual RCCS and downscaled heat-removal test facility
Annals of Nuclear Energy, 133, p.830 - 836, 2019/11
O. Myagmarjav, N. Tanaka, M. Nomura, S. Kubo
Comparison of experimental and simulation results on catalytic HI decomposition in a silica-based ceramic membrane reactor
International Journal of Hydrogen Energy, 44(59), p.30832 - 30839, 2019/11
Y. Fukaya, S. Nakagawa, M. Goto, E. Ishitsuka, S. Kawakami, T. Uesaka, K. Morita, T. Sano
Reactor physics experiment in graphite moderation system for HTGR, 1
KURNS Progress Report 2018, P. 148, 2019/08
Y. Fukaya
Study on levelizing electricity generation cost for nuclear power generation between generations
Meruko Kanri Kaikei Kenkyu, (11-2), p.45 - 62, 2019/05
O. Myagmarjav, N. Tanaka, M. Nomura, S. Kubo
Module design of silica membrane reactor for hydrogen production via thermochemical IS process
International Journal of Hydrogen Energy, 44(21), p.10207 - 10217, 2019/04
Y. Inagaki, N. Sakaba
Development of hydrogen production technology by thermal water splitting with solar heat
Shokubai, 61(2), p.92 - 96, 2019/04

国際会議

H. Sato, H. Ohashi
Uncertainty analysis of toxic gas leakage accident in cogeneration high temperature gas-cooled reactor
27th International Conference on Nuclear Engineering (ICONE-27),Tsukuba,Japan,May 19-24,2019.
S. Takada, I. W. Narayana, Y. Nakatsuru, A. Terada, K. Murakami, K. Sawa
Establishment of numerical model to investigate heat transfer and flow characteristics by using scale model of vessel cooling system for HTTR
27th International Conference on Nuclear Engineering (ICONE-27),Tsukuba,Japan,May 19-24,2019.
I. Ioka, Y. Kuriki, J. Iwatsuki, S. Kubo, Y. Inagaki, N. Sakaba
Development of container using plasma sprayed and laser treated material for sulfuric acid decomposition of thermochemical water-splitting iodine-sulfur process
27th International Conference on Nuclear Engineering (ICONE-27),Tsukuba,Japan,May 19-24,2019.
S. Ueta, N. Mizuta, K. Sasaki, N. Sakaba, H. Ohashi, X. Yan
Research and development on high burnup HTGR fuels in JAEA
27th International Conference on Nuclear Engineering (ICONE-27),Tsukuba,Japan,May 19-24,2019.
N. Mizuta, T. Aoki, S. Ueta, H. Ohashi, X. Yan
Study of SiC-matrix fuel element for HTGR
27th International Conference on Nuclear Engineering (ICONE-27),Tsukuba,Japan,May 19-24,2019.

公開報告書等

高温工学試験研究炉部
HTTR(高温工学試験研究炉)の試験・運転と技術開発(2018年度)
JAEA-Review 2019-049
相原 純、後藤 実、植田 祥平、橘 幸男
被覆燃料粒子の応力計算のためのCode-B-2.5.2
JAEA-Data/Code 2019-018
小野 正人、小澤 太教、藤本 望
HTTRの起動用中性子源の交換時期の推定
JAEA-Technology 2019-012
M. Ogawa
Flow separation at inlet causing transition and intermittency in circular pipe flow
JAEA-Technology 2019-010
石塚 悦男、松中 一朗、石田 大樹、H. Q. Ho、石井 俊晃、濱本 真平、高松 邦吉I. Kenzhina、Y. Chikhray、近藤 篤、高木 直行、藤本 望
2018年度夏期休暇実習報告; HTTR炉心を用いた原子力電池に関する予備的検討; 核設計のための予備検討
JAEA-Technology 2019-008
高温工学試験研究炉部
HTTR(高温工学試験研究炉)の試験・運転と技術開発; 2017年度
JAEA-Review 2019-006