Results for FY '18

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Papers

J. Aihara, M. Honda, S. Ueta, H. Ogawa, K. Ohira, Y. Tachibana
Development of fabrication technology for oxidation-resistant fuel elements for high-temperature gas-cooled reactors
Nippon Genshiryoku Gakkai Wabun Rombunshi, 18(1), p.29 - 36, 2019/03
H. Sato, X. Yan
Study of an HTGR and renewable energy hybrid system for grid stability
Nuclear Engineering and Design, 343, p.178 - 186, 2019/03
K. Takamatsu, T. Matsumoto, W. Liu, K. Morita
Improvement of heat-removal capability using heat conduction on a novel reactor cavity cooling system (RCCS) design with passive safety features through radiation and natural convection
Annals of Nuclear Energy, 122, p.201 - 206, 2018/12
M. Goto, K. Okumura, S. Nakagawa, Y. Inaba, H. Matsuura, H. Nakaya, K. Katayama
Nuclear and thermal feasibility of lithium-loaded high temperature gas-cooled reactor for tritium production for fusion reactors
Fusion Engineering and Design, 136(Part A), p.357 - 361, 2018/11
Y. Fukaya, M. Goto, H. Ohashi, X. Yan, T. Nishihara, Y. Tsubata, T. Matsumura
Uranium-based TRU multi-recycling with thermal neutron HTGR to reduce environmental burden and threat of nuclear proliferation
Journal of Nuclear Science and Technology, 55(11), p.1275 - 1290, 2018/11
H. Q. Ho, Y. Honda, S. Hamamoto, T. Ishii, N. Fujimoto, E. Ishitsuka
Feasibility study of large-scale production of iodine-125 at the high temperature engineering test reactor
Applied Radiation and Isotopes, 140, p.209 - 214, 2018/10
S. Ueta, J. Aihara, M. Goto, Y. Tachibana, K. Okamoto
Development of security and safety fuel for Pu-burner HTGR; Test and characterization for ZrC coating
Mechanical Engineering Journal (Internet), 5(5), p.18-00084_1 - 18-00084_9, 2018/10
M. Nomura, T. Kodaira, A. Ikeda, Y. Naka, H. Nishijima, S. Imabayashi, S. Sawada, T. Yamaki, N. Tanaka, S. Kubo
Development of ion-exchange membranes for the membrane Bunsen reaction in thermochemical hydrogen production by iodine-sulfur process
Journal of Chemical Engineering of Japan, 51(9), p.726 - 731, 2018/09
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
Journal of Nuclear Engineering and Radiation Science, 4(3), p.031013_1 - 031013_11, 2018/07
Y. Fukaya, M. Goto, H. Ohashi, T. Nishihara, Y. Tsubata, T. Matsumura
Optimization of disposal method and scenario to reduce high level waste volume and repository footprint for HTGR
Annals of Nuclear Energy, 116, p.224 - 234, 2018/06
H. Q. Ho, Y. Honda, M. Motoyama, S. Hamamoto, T. Ishii, E. Ishitsuka
Proposal of a neutron transmutation doping facility for n-type spherical silicon solar cell at high-temperature engineering test reactor
Applied Radiation and Isotopes, 135, p.12 - 18, 2018/05
Y. Fukaya
Safety and economics of uranium utilization for nuclear power generation
Uranium; Safety, Resources, Separation and Thermodynamic Calculation, p.22 - 48, 2018/05
M. Ono, K. Iigaki, H. Sawahata, Y. Shimazaki, A. Shimizu, H. Inoi, T. Kondo, K. Kojima, S. Takada, K. Sawa
Comprehensive seismic evaluation of HTTR against the 2011 off the Pacific coast of Tohoku Earthquake
Journal of Nuclear Engineering and Radiation Science, 4(2), p.020906_1 - 020906_8, 2018/04
K. Kunitomi, T. Nishihara, X. Yan, Y. Tachibana, T. Shibata
The Development status of Generation IV reactor systems, 2; High temperature gas-cooled reactor (HTGR)
Nippon Genshiryoku Gakkai-Shi, 60(4), p.236 - 240, 2018/04
S. Kasahara, Y. Imai, K. Suzuki, J. Iwatsuki, A. Terada, X. Yan
Conceptual design of the iodine-sulfur process flowsheet with more than 50% thermal efficiency for hydrogen production
Nuclear Engineering and Design, 329, p.213 - 222, 2018/04
H. Sato, Y. Nomoto, S. Horii, J. Sumita, X. Yan
HTTR-GT/H test plant; System performance evaluation for HTTR gas turbine cogeneration plant
Nuclear Engineering and Design, 329, p.247 - 254, 2018/0
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
Design of HTTR-GT/H test plant
Nuclear Engineering and Design, 329, p.223 - 233, 2018/04

International Conference

S. Hosomi, T. Akashi, T. Matsumoto, W. Liu, K. Morita, K. Takamatsu
Experimental study on heat removal performance of a new Reactor Cavity Cooling System (RCCS)
11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11), Busan, Korea, November 18-21, 2018.
H. Q. Ho, Y. Honda, S. Hamamoto, T. Ishii, S. Takada, N. Fujimoto, E. Ishitsuka
Feasibility study of new applications at the high-temperature gas-cooled reactor
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
H. Takegami, H. Noguchi, N. Tanaka, J. Iwatsuki, Y. Kamiji, S. Kasahara, Y. Imai, A. Terada, S. Kubo
Current R&D status of thermochemical water splitting hydrogen production iodine-sulfur process in Japan Atomic Energy Agency, 1; Hydrogen production test and component development
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
Y. Kamiji, H. Noguchi, H. Takegami, N. Tanaka, J. Iwatsuki, S. Kasahara, S. Kubo
Current R&D status of thermochemical water splitting hydrogen production iodine-sulfur process in Japan Atomic Energy Agency, 2; Reliability improvements of corrosion-resistant equipment
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
J. Iwatsuki, H. Ohashi, X. Yan
Conceptual design of the steam reforming system for hydrogen production connected to HTTR
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
Y. Fukaya, M. Goto, S. Ueta, Y. Tachibana, K. Okamoto
Study on Pu-burner high temperature gas-cooled reactor in Japan; Introduction scenario
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018
Y. Fukaya, N. Mizuta, M. Goto, H. Ohashi, X. Yan
Conceptual design study of a high performance commercial HTGR
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
H. Ohashi, M. Goto, S. Ueta, H. Sato, Y. Fukaya, S. Kasahara, K. Sasaki, N. Mizuta, X. Yan, T. Aoki
Conceptual plant system design study of an experimental HTGR upgraded from HTTR
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
M. Goto, Y. Fukaya, N. Mizuta, Y. Inaba, H. Ohashi, X. Yan
Conceptual study of an experimental HTGR upgraded from HTTR
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
M. Goto, J. Aihara, Y. Inaba, S. Ueta, Y. Fukaya, K. Okamoto
Study on Pu-burner high temperature gas-cooled reactor in Japan; Design study of fuel and reactor core
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
T. Ishii, Y. Shimazaki, M. Ono, Y. Fujiwara, E. Ishitsuka, S. Hamamoto
Study on source of radioactive material in primary coolant of HTTR
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
S. Ueta, J. Aihara, N. Mizuta, M. Goto, Y. Fukaya, Y. Tachibana, K. Okamoto
Study on Pu-burner high temperature gas-cooled reactor in Japan; Test and characterization for ZrC coating
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
A. Shaimerdenov, S. Gizatulin, Y. Kenzhin, D. Dyussambayev, S. Ueta, J. Aihara, T. Shibata
Investigation of irradiated properties of extended burnup TRISO fuel
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
S. Takada, Y. Honda, Y. Inaba, K. Sekita, T. Nemoto, D. Tochio, T. Ishii, H. Sato, S. Nakagawa, K. Sawa
Numerical evaluation on fluctuation absorption characteristics based on nuclear heat supply fluctuation test using HTTR
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
H. Sato, H. Ohashi, X. Yan
Research and development for safety and licensing of HTGR cogeneration system
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
P. W. Humrickhouse, H. Sato, Y. Imai, J. Sumita, X. Yan
RELAP5 modeling of the HTTR-GT/H secondary system and turbomachinery
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
M. A. Futterer, F. Li, H. Gougar, L. Edwards, M. A. Pouchon, M. H. Kim, F. Carre, H. Sato
Recent advances in the GIF very high temperature reactor system
9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018), Warsaw, Poland, October 8-10, 2018.
N. Hirota, A. Terada, X. Yan, K. Tanaka, A. Otani
A Concept of intermediate heat exchanger for high-temperature gas reactor hydrogen and power cogeneration system
26th International Conference on Nuclear Engineering (ICONE-26),London,U.K.,July 22-28,2018.

Reports

E. Ishitsuka, I. Kenzhina, K. Okumura, H. Q. Ho, N. Takemoto, Y. Chikhray
Calculations of Tritium Recoil Release from Li and U Impurities in Neutron Reflectors (Joint Research)
JAEA-Technology 2018-010
T. Nishihara, X. Yan, Y. Tachibana, T. Shibata, H. Ohashi, S. Kubo, Y. Inaba, S. Nakagawa, M. Goto, S. Ueta, Shohei, N. Hirota, Y. Inagaki, K. Iigaki, S. Hamamoto, K. Kunitomi
Excellent feature of Japanese HTGR technologies
JAEA-Technology 2018-004
J. Aihara, S. Ueta, M. Goto, Y. Inaba, T. Shibata, H. Ohashi
Comparison between HTFP Code and Minory Changed FORNAX-A Code
JAEA-Technology 2018-002
Y. Fukaya, S. Kasahara, N. Mizuta, Y. Inaba, T. Shibata, T. Nishihara
Research on Demand of HTGR for Investigation of Introduction Scenario and Investigation on Heat Balance of HTGR
JAEA-Research 2018-004
K. Tatematsu, T. Nishihara
Assessment Report on Research and Development Activities in FY2017 Activity: "Research and Development on High Temperature Gas-cooled Reactor and Related Heat Application Technology" (Annual Report)
JAEA-Evaluation 2018-001