References
- S. Fujikawa, H. Hayashi, T. Nakazawa, K. Kawasaki, T. Iyoku, S. Nakagawa and N. Sakaba, 'Achievement of Reactor-Outlet Coolant Temperature of 950C in HTTR', Journal of Nuclear Science and Technology, Vol.41, No.12, p1245-1254, (2004) https://doi.org/10.3327/jnst.41.1245
- K. Kunitomi, S. Katanishi, S. Takada, T. Takizuka and X. Yan, 'Japan's future HTR-GTHTR300', Nuclear Engineering Design 233, p309-327, (2004)
- Shinji Kubo, Hayato Nakajima, Seiji Kasahara, Syunichi Higashi, Tomoo Masaki, Hiroyoshi Abe and Kaoru Onuki, 'A demonstration study on a closed-cycle hydrogen production by the thermochemical water-splitting iodine–sulfur process', Nuclear Engineering Design 233, p347-354, (2004) https://doi.org/10.1016/j.nucengdes.2004.08.025
- J.H. Norman, G.E. Besenbruch, L.C. Brown, D.R. O'Keefe, C.L. Allen, Thermochemical water-splitting cycle, benchscale investigations, and process engineering, DOE/ET/ 26225-1, GA-A16713, (1982)
- M. Roth and K.F. Knoche, Int. J. Hydrogen Energy, 14, p545-549, (1989) https://doi.org/10.1016/0360-3199(89)90112-2
- I.T. Oeztuerk, A. Hammache, E. Bilgen, Trans. IChemE., 72 Part A, p241-250, (1989)
- H. Nakajima, M. Sakurai, K. Ikenoya, G.-J. Hwang, K. Onuki, S. Shimizu, A study on a closed-cycle hydrogen production by thermochemical water-splitting IS process, Proc. 7th Int. Conf. Nuclear Engineering (ICONE-7), Tokyo, Japan, April 1999, ICONE-7104
- K. Kunitomi, M. Shinozaki, M. Ohkubo, and et al., 'Stress and strain evaluation of heat transfer tubes in intermediate heat exchanger for HTTR, Proc. of 2nd ASME/JAME Nuclear Engineering Conference, Vol.2, p847-853, (1993)
- K. Kunitomi, S. Katanishi, S. Takada and et al., 'Reactor Core Design of Gas Turbine High Temperature Reactor 300', Nuclear Engineering Design, 230, p349-366, (2004) https://doi.org/10.1016/j.nucengdes.2003.11.028
- T. Takeda et al., Deployment Scenario of GTHTR300 Cogeneration System, Proceedings of GLOBAL 2005, Paper No.325, (2005)
- Japan Atomic Energy Commission, Document No. 13 in the 9th New Nuclear Policy-planning Council, Analysis of nuclear fuel cycle parameters (revised) http://aec.jst.go.jp/ jicst/NC/tyoki/sakutei2004/sakutei09/siryo13.pdf, (2004)
Cited by
- Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System vol.133, pp.2, 2011, https://doi.org/10.1115/1.4002351
- Study of an incrementally loaded multistage flash desalination system for optimum use of sensible waste heat from nuclear power plant vol.37, pp.14, 2012, https://doi.org/10.1002/er.2995
- Evaluation of high temperature gas reactor for demanding cogeneration load follow vol.49, pp.1, 2012, https://doi.org/10.1080/18811248.2011.636564
- A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries vol.2013, pp.2314-6060, 2013, https://doi.org/10.1155/2013/918567
- Evaluation of GTHTR300A nuclear power plant design with dry cooling vol.38, pp.11, 2014, https://doi.org/10.1002/er.3172
- Research and developments on application of carbon-carbon composite to HTGR/VHTR in Japan vol.18, pp.16, 2011, https://doi.org/10.1088/1757-899X/18/16/162003