Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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PERSPECTIVES OF NUCLEAR HEAT AND HYDROGEN

  • Published : 2009.05.31
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Abstract

Nuclear energy plays an important role in world energy production by supplying 6% of the world's current total electricity production. However, 86% of the energy consumed worldwide to produce industrial process heat, to generate electricity and to power the transportation sector still originates in fossil fuels. To cope with dwindling fossil fuels and climate change, it is clear that a clean alternative energy that can replace fossil fuels in these sectors is urgently required. Clean hydrogen energy is one such alternative. Clean hydrogen can play an important role not only in synthetic fuel production but also through powering fuel cells in the anticipated hydrogen economy. With the introduction of the high temperature gas-cooled reactor (HTGR) that can produce nuclear heat up to $950^{\circ}C$ without greenhouse gas emissions, nuclear power is poised to broaden its mission beyond electricity generation to the provision of nuclear process heat and the massive production of hydrogen. In this paper, the features and potential of the HTGR as the energy source of the future are addressed. Perspectives on nuclear heat and hydrogen applications using the HTGR are discussed.

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References

  1. R. Jeremy, The Hydrogen Economy, (2002)
  2. Energy Information Administration, http://www.eia.doe.gov/
  3. K.J. Bu, “National Vision for Hydrogen Economy and Its Action plan Set up,” Energy Economy Research, 4(2), 129-147, (2005)
  4. J. Chang, Y.W. Kim, K.Y. Lee, Y.W. Lee, W.J. Lee, J.M. Noh, M.H. Kim, H.S. Lim, Y.J. Shin, K.K. Bae, and K.D. Jung, “A Study of a Nuclear Hydrogen production Demonstration Plant,” Nuclear Engineering and Technology, 39(2), 111-122, (2007) https://doi.org/10.5516/NET.2007.39.2.111
  5. M. Richards and A. Shenoy, “H2-MHR Pre-conceptual Design Summary for Hydrogen Production,” Nuclear Engineering and Technology, 39(1), 1-8(2007) https://doi.org/10.5516/NET.2007.39.1.001
  6. H. Nabielek, W. Kuhnlein, W. Schenk, W. Heit, A. Christ, H. Ragoss, “Development of Advanced HTR Fuel Elements,” Nuclear Engineering and Design, 121, 199-210, (1990) https://doi.org/10.1016/0029-5493(90)90105-7
  7. R. A. Simon and P. D. Capp, “Operating Experience with the Dragon High Temperature Reactor Experiment) by Reverses Osmosis(RO),” Proceedings of 1st International Topical Meeting on HTR, Petten, April.22-24, (2002)
  8. K.I. Kingrey, Fuel Summary for Peach Bottom Unit 1 High- Temperature Gas-Cooled Reactor Cores 1 and 2, INEEL/ EXT-03-00103, (2003)
  9. E. Wahlen and P. Pohl, AVR Operational Experience, Overview, FZJ, (2001)
  10. S. Saito et al. Design of High Temperature Engineering Test Reactor (HTTR), JAERI-1332, (1994)
  11. D. Zhong and Y. Xu, Progress of the HTR-10 project, IAEATECDOC- 899, (1995)
  12. F.A.Silady, J.C.Cunliffe, and L.P.Walker, “The Licensing Experience of the Modular High-Temperature Gas-Cooled Reactor (MHTGR),” Proc. of TCM, SanDiego, 21-23 Sept. (1988)
  13. A. Shenoy, Gas Turbine Modular Helium Reactor (GT-MHR) Conceptual Design Description Report, GA report 910720, (1996)
  14. Z. Wu and Y. Dong, “Introduction of HTR-PM Demonstration Project,” Proceedings of IAEA TM on Safety Aspects of Modular HTGRs, Beijing, 23-26 Oct. (2007)
  15. K. Weaver, et.al, NGNP Preliminary Project Management Plan, INL/EXT-05-00952, (2006)
  16. K. Kunitomi, et al., 'JAEA's VHTR for Hydrogen and Electricity Cogeneration: GTHTR300C,' Nuclear Engineering and Technology, 39(1), 9-20, (2007)' https://doi.org/10.5516/NET.2007.39.1.009
  17. S.A. Wright and P.S. Pickard, “Impact of Closed Brayton Cycle Test Results on Gas Cooled Reactor Operation and Safety,” Proceedings of ICAPP 2007, Nice, France, May 13-18, (2007)
  18. M. Richards, et al., “VHTR Deep Burn Applications,” Proceedings of PBNC-16, Aomori, Japan, Oct. 13-18, (2008)
  19. D. Hinttner, et al., “A New Impetus for Developing Industrial Process Heat Applications of HTR in Europe,” Proceedings of HTR 2008, Washington DC, Sept30-Oct.1, (2008) https://doi.org/10.1115/HTR2008-58259
  20. Y.W. Kim, et al., “Gas Cooled Reactor, Its Potential Applications for Process Heat” IAEA TM on Non electric Applications of Nuclear Energy, Daejeon, March 3-6, (2009)
  21. W. Kriel, et al., “The Potential of the PBMR for Process Heat Applications,” Proceedings HTR-2006, Johannesburg, RSA, Oct.1-4, 2006
  22. J. Chang “Challenges for Production of Hydrogen Using Nuclear Energy,” IAEA TM on Non electric Applications of Nuclear Energy, Daejeon, March 3-6, (2009)
  23. M. Ogawa, Nishihara, “Japan's HTTR, Tetsuo,” Nuclear Engineering and Design, 233(1-3), 5-10, (2004) https://doi.org/10.1016/j.nucengdes.2004.07.018
  24. R. Elder and R. Allen, “Nuclear Heat for Hydrogen Production : Coupling a Very High/High Temperature Reactor to a Hydrogen Production Plant,” Progress in Nuclear Energy, 51, 500-525, (2009) https://doi.org/10.1016/j.pnucene.2008.11.001
  25. R. Kuhr, “HTR’s Role in Process Heat Application,” Nuclear Engineering and Design, 238(11) 3013-3017, (2008) https://doi.org/10.1016/j.nucengdes.2008.02.018
  26. H. Ohashi et al., “Development of Control Technology for HTTR Hydrogen Production System with Mock-up Test Facility - System Controllability Test for Loss of Chemical Reaction.” Nuclear Engineering and Design 236, 1396- 1410, (2006) https://doi.org/10.1016/j.nucengdes.2006.01.005
  27. K. Suruoka, T. Inatani, T. Miyasugi, and M. Mizuno, “Design Study of Nuclear Steelmaking System,” Transaction of the Iron and Steel Institute of Japan, 23(12), 1091-1101, (1983) https://doi.org/10.2355/isijinternational1966.23.1091
  28. J. Astier, J.C. Krug and Y. De Lassat de Pressigny, 'Technico- Economic Potentialities of Hydrogen Utilization for Steel Production,' Int. J. Hydrogen Energy, 7(8), 671-679, (1982) https://doi.org/10.1016/0360-3199(82)90192-6
  29. C. O. Bolthrunis, R. Kuhr, A.E. Finan, “Using a PBMR to Heat a Steam-Methane Reformer: Technology and Economics,” Proceedings of the 3rd International Topical Meeting on High Temperature Reactor Technology, Paper 100000118, (2006)
  30. W.J. Lee, et al., “Status of Nuclear Hydrogen Project in Korea”, ANS Embedded Topical on ST-NH2, Boston, USA, Jun 24~28 (2007)
  31. C.K. Jo and J.M Noh, “Preliminary Core Design Analysis of a 200MWth Pebble Bed-type VHTR,” Proceedings. of the Korean Nuclear Society Spring Meeting, Jeju, Korea, (2007)
  32. M.H. Kim, et al. “Computational Assessment of the Vessel Cooling Design Options for a VHTR,” Proceedings of the Korean Nuclear Society Autumn Meeting, Pyeongchang, Oct.30-31, Korea, (2008)
  33. Y. Shin, Pre-evaluation of Nuclear Hydrogen process, NHDD-HI-CA-08-06, KAERI Report, (2008)

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