Results for FY '15
Papers
- 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.
- Y. Fukaya, K. Kunitomi, M. Ogawa
- Study on reduction of potential radiotoxicity for spent fuel by using HTGR
- Transactions of the Atomic Energy Society of Japan, 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)69-79
- 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
International Conference
- 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
Reports
- K. Tatematsu, H. Matsumoto
- Assessment report of research and development activities in FY2014; Activity "Research and development on high-temperature gas-cooled reactor and related hydrogen production technology"
- JAEA-Evaluation 2015-001
- Y. Nomoto, J. Aihara, S. Nakagawa, K. Isaka, H. Ohashi
- HTFP for calculation of amount of additionally released fission products from fuel rods of pin-in-block-type high temperature gas-cooled reactors during accident
- JAEA-Data/Code 2015-008
- Y. Fukaya, M. Goto, T. Nishihara
- Study on innovative HTGR to reduce generation of potential radiotoxicity
- JAEA-Research 2015-023
- Y. Fukaya, M. Goto, T. Nishihara
- Development on nuclear design model for detailed design of clean burn HTGR
- JAEA-Technology 2015-017
- J. Aihara, S. Ueta, T. Nishihara
- Application of FORNAX-A
- 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 Institute, Oarai, Japan
- JAEA-Review 2015-04
- S. Kubo, J. Iwatsuki, H. Takegami, S. Kasahara, N. Tanaka, H. Noguchi, Y. Kamiji, K. Onuki
- Research and development on chemical reactors made of industrial structural materials and hydriodic acid concentration technique for thermochemical hydrogen production IS process
- JAEA-Technology 2015-028