Results for FY '20

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N. Hirota, K. Takeda, Y. Tachibana, Y. Masaki
Corrosion resistance and oxide film structure of stainless steels and Ni-based alloys under sulfuric decomposition gas at high temperature
zairyo-to-kankyo, 70(3), p.68-76, 2021/03
K. Takamatsu, T. Matsumoto, W. Liu, K. Morita
Comparison between passive reactor cavity cooling systems based on atmospheric radiation and atmospheric natural circulation
Annals of Nuclear Energy, 151, p.107867_1 - 107867_11, 2021/02
Y. Fukaya, S. Ueta, M. Goto, H. Ohashi
Feasibility study on burnable poison credit concept to HTGR fuel fabrication from core specification perspective
Annals of Nuclear Energy, 151( ), p.107937_1 - 107937_9, 2021/02
T. Aoki, S. S. Chirayath, H. Sagara
Proliferation resistance evaluation of an HTGR transuranic fuel cycle using PRAETOR code
Annals of Nuclear Energy, 141, p.107325_1 - 107325_7, 2020/06
H. Sato, H. Ohashi
Uncertainty analysis of toxic gas leakage accident in cogeneration high temperature gas-cooled reactor
Mechanical Engineering Journal (Internet), 7(3), p.19-00332_1 - 19-00332_11, 2020/06
S. Takada, I. W. Ngarayana, Y. Nakatsuru, A. Terada, K. Murakami, K. Sawa
Establishment of reasonable 2-D model to investigate heat transfer and flow characteristics by using scale model of vessel cooling system for HTTR
Mechanical Engineering Journal (Internet), 7(3), p.19-00536_1 - 19-00536_12, 2020/06
S. Ueta, N. Mizuta, K. Sasaki, N. Sakaba, H. Ohashi, X. L. Yan
Research and development on high burnup HTGR fuels in JAEA
Mechanical Engineering Journal (Internet), 7(3), p.19-00571_1 - 19-00571_12, 2020/06
I. Ioka, J. Iwatsuki, Y. Kuriki, D. Kawai, H. Yokota, S. Kubo, Y. Inagaki, N. Sakaba
Study of container using hybrid technique for sulfuric acid decomposition of thermochemical water-splitting iodine-sulfur process
Mechanical Engineering Journal (Internet), 7(3), p.19-00377_1 - 19-00377_11, 2020/06
M. Ono, Y. Fujiwara, T. Matsumoto, K. Iigaki
Evaluation of impact with high temperature engineering test reactor using realistic model of stack and reactor building
Transactions of the Atomic Energy Society of Japan, 19(2), p.110 - 120, 2020/06
Y. Fukaya, N. Mizuta, M. Goto, H. Ohashi, X. L. Yan
Conceptual design study of a high performance commercial HTGR for early introduction
Nuclear Engineering and Design, 361, p.110577_1 - 110577_6, 2020/05
Y. Kamiji, H. Noguchi, H. Takegami, N. Tanaka, J. Iwatsuki, S. Kasahara, S. Kubo
Reliability improvements of corrosion-resistant equipment for thermochemical water splitting hydrogen production iodine-sulfur process
Nuclear Engineering and Design, 361, p.110573_1 - 110573_6, 2020/05
Y. Fukaya, M. Goto, H. Ohashi
Self-shielding effect of double heterogeneity for plutonium burner HTGR design
Annals of Nuclear Energy, 138, p.107182_1 - 107182_9, 2020/04
H. Q. Ho, Y. Honda, S. Hamamoto, T. Ishii, S. Takada, N. Fujimoto, E. Ishitsuka
Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor
Journal of Nuclear Engineering and Radiation Science, 6(2), p.021902_1 - 021902_6, 2020/04
H. Sato, T. Aoki, H. Ohashi, X. L. Yan
Research and development for safety and licensing of HTGR cogeneration system
Nuclear Engineering and Design, 360, p.110493_1 - 110493_8, 2020/04
H. Takegami, H. Noguchi, N. Tanaka, J. Iwatsuki, Y. Kamiji, S. Kasahara, Y. Imai, A. Terada, S. Kubo
Development of strength evaluation method of ceramic reactor for iodine-sulfur process and hydrogen production test in Japan Atomic Energy Agency
Nuclear Engineering and Design, 360, p.110498_1 - 110498_6, 2020/04

International Conference

H. Sato, T. Aoki, H. Ohashi
Guidance for Developing Fuel Design Limit of High Temperature Gas-Cooled Reactor
Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 10 Pages, 2020/08
T. Aoki, H. Sato, H. Ohashi
Methodology Development for Transient Flow Distribution Analysis in High Temperature Gas-Cooled Reactor
Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 6 Pages, 2020/08
T. Aoki, K. Isaka, H. Sato, H. Ohashi
Development of a Flow Network Calculation Code (FNCC) for High Temperature Gas-Cooled Reactors (HTGRs)
Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 7 Pages, 2020/08
T. Shibata, H. Sato, S. Ueta, H. Takegami, S. Takada, K. Kunitomi
VHTR technology development in Japan; Progress of R&D activities for GIF VHTR system
2018 GIF Symposium Proceedings (Internet), p.99 - 106, 2020/05


M. Ono, Y. Hanawa, H. Sonobe, A. Nishimura, N. Sugaya, K. Iigaki
Assessment of the Probability of Aircraft Crashing for HTTR
JAEA-Technology 2020-010
E. Ishitsuka, K. Nakashima, N. Nakagawa, H. Q. HO, T. Ishi, S. Hamamoto, K. Takamatsu, I. Kenzhina, Y. Chikhray, H. Matsuura, N. Fujimoto
Report of Summer Holiday Practical Training 2019; Feasibility Study on Nuclear Battery using HTTR Core -Feasibility Study for Nuclear Design (2)-
JAEA-Technology 2020-008
Sector of Fast Reactor and Advanced Reactor Research and Development
Assessment Report on Research and Development Activities in FY2019 Activity “Research and Development on High Temperature Gas-cooled Reactor and Related Heat Application Technology” (Interim Report)
JAEA-Evaluation 2020-001
S. Nagasumi, K. Matsunaka, N. Fujimoto, T. Ishii, E. Ishitsuka
Study on Control Rod Model in HTTR Core Analysis
JAEA-Technology 2020-003