Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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JAEA'S VHTR FOR HYDROGEN AND ELECTRICITY COGENERATION : GTHTR300C

  • Kunitomi, Kazuhiko (Cogeneration HTGR Design and Assessment Group Nuclear Applied Heat Technology Division Japan Atomic Energy Agency) ;
  • Yan, Xing (Cogeneration HTGR Design and Assessment Group Nuclear Applied Heat Technology Division Japan Atomic Energy Agency) ;
  • Nishihara, Tetsuo (Cogeneration HTGR Design and Assessment Group Nuclear Applied Heat Technology Division Japan Atomic Energy Agency) ;
  • Sakaba, Nariaki (Cogeneration HTGR Design and Assessment Group Nuclear Applied Heat Technology Division Japan Atomic Energy Agency) ;
  • Mouri, Tomoaki (Cogeneration HTGR Design and Assessment Group Nuclear Applied Heat Technology Division Japan Atomic Energy Agency)
  • Published : 2007.02.28
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Abstract

Design study on the Gas Turbine High Temperature Reactor 300-Cogeneration (GTHTR300C) aiming at producing both electricity by a gas turbine and hydrogen by a thermochemical water splitting method (IS process method) has been conducted. It is expected to be one of the most attractive systems to provide hydrogen for fuel cell vehicles after 2030. The GTHTR300C employs a block type Very High Temperature Reactor (VHTR) with thermal power of 600MW and outlet coolant temperature of $950^{\circ}C$. The intermediate heat exchanger (IHX) and the gas turbine are arranged in series in the primary circuit. The IHX transfers the heat of 170MW to the secondary system used for hydrogen production. The balance of the reactor thermal power is used for electricity generation. The GTHTR300C is designed based on the existing technologies of the High Temperature Engineering Test Reactor (HTTR) and helium turbine power conversion and on the technologies whose development have been well under way for IS hydrogen production process so as to minimize cost and risk of deployment. This paper describes the original design features focusing on the plant layout and plant cycle of the GTHTR300C together with present development status of the GTHTR300, IHX, etc. Also, the advantage of the GTHTR300C is presented.

Keywords

References

  1. 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
  2. K. Kunitomi, S. Katanishi, S. Takada, T. Takizuka and X. Yan, 'Japan's future HTR-GTHTR300', Nuclear Engineering Design 233, p309-327, (2004)
  3. 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
  4. 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)
  5. M. Roth and K.F. Knoche, Int. J. Hydrogen Energy, 14, p545-549, (1989) https://doi.org/10.1016/0360-3199(89)90112-2
  6. I.T. Oeztuerk, A. Hammache, E. Bilgen, Trans. IChemE., 72 Part A, p241-250, (1989)
  7. 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
  8. 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)
  9. 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
  10. T. Takeda et al., Deployment Scenario of GTHTR300 Cogeneration System, Proceedings of GLOBAL 2005, Paper No.325, (2005)
  11. 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)

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