Results for FY '19
Papers
- 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
International Conference
- 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.
Reports
- Department of HTTR
- Operation, Test, Research and Development of the High Temperature Engineering Test Reactor (HTTR) (FY2018)
- JAEA-Review 2019-049
- J. Aihara, M. Goto, S. Ueta, Y. Tachibana
- Code-B-2.5.2 for Stress Calculation for SiC-TRISO Fuel Particle
- JAEA-Data/Code 2019-018
- M. ONO, T. Kozawa, N. Fujimoto
- Estimation of Exchange Time for Neutron Startup Sources of HTTR
- JAEA-Technology 2019-012
- M. Ogawa
- Flow separation at inlet causing transition and intermittency in circular pipe flow
- JAEA-Technology 2019-010
- E. Ishitsuka, I. Matsunaka, H. Ishida, H. Q. Ho, T. Ishii, S. Hamamoto, K. Takamatsu, I. Kenzhina, Y. Chikhray, A. Kondo, T. Takaki, N. Fujimoto
- Report of Summer Holiday Practical Training 2018; Feasibility Study on Nuclear Battery using HTTR Core -Feasibility Study for Nuclear Design-
- JAEA-Technology 2019-008
- Department of HTTR
- Operation, Test, Research and Development of the High Temperature Engineering Test Reactor (HTTR) (FY2017)
- JAEA-Review 2019-006