Browse > Article
http://dx.doi.org/10.5516/NET.2009.41.4.413

PERSPECTIVES OF NUCLEAR HEAT AND HYDROGEN  

Lee, Won-Jae (Korea Atomic Energy Research Institute)
Kim, Yong-Wan (Korea Atomic Energy Research Institute)
Chang, Jong-Hwa (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.41, no.4, 2009 , pp. 413-426 More about this Journal
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.
Keywords
HTGR; AHTGR; VHTR; Nuclear Process Heat; Nuclear Hydrogen; NHDD;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
Times Cited By Web Of Science : 0  (Related Records In Web of Science)
연도 인용수 순위
1 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)
2 W. Kriel, et al., “The Potential of the PBMR for Process Heat Applications,” Proceedings HTR-2006, Johannesburg, RSA, Oct.1-4, 2006
3 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)   DOI   ScienceOn
4 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)
5 W.J. Lee, et al., “Status of Nuclear Hydrogen Project in Korea”, ANS Embedded Topical on ST-NH2, Boston, USA, Jun 24~28 (2007)
6 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)
7 Energy Information Administration, http://www.eia.doe.gov/
8 R. Jeremy, The Hydrogen Economy, (2002)
9 M. Ogawa, Nishihara, “Japan's HTTR, Tetsuo,” Nuclear Engineering and Design, 233(1-3), 5-10, (2004)   DOI   ScienceOn
10 Y. Shin, Pre-evaluation of Nuclear Hydrogen process, NHDD-HI-CA-08-06, KAERI Report, (2008)
11 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)   DOI   ScienceOn
12 M. Richards, et al., “VHTR Deep Burn Applications,” Proceedings of PBNC-16, Aomori, Japan, Oct. 13-18, (2008)
13 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)   DOI   ScienceOn
14 K. Kunitomi, et al., 'JAEA's VHTR for Hydrogen and Electricity Cogeneration: GTHTR300C,' Nuclear Engineering and Technology, 39(1), 9-20, (2007)'   과학기술학회마을   DOI
15 J. Chang “Challenges for Production of Hydrogen Using Nuclear Energy,” IAEA TM on Non electric Applications of Nuclear Energy, Daejeon, March 3-6, (2009)
16 S. Saito et al. Design of High Temperature Engineering Test Reactor (HTTR), JAERI-1332, (1994)
17 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)
18 E. Wahlen and P. Pohl, AVR Operational Experience, Overview, FZJ, (2001)
19 R. Kuhr, “HTR’s Role in Process Heat Application,” Nuclear Engineering and Design, 238(11) 3013-3017, (2008)   DOI   ScienceOn
20 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)   DOI
21 M. Richards and A. Shenoy, “H2-MHR Pre-conceptual Design Summary for Hydrogen Production,” Nuclear Engineering and Technology, 39(1), 1-8(2007)   DOI
22 K.J. Bu, “National Vision for Hydrogen Economy and Its Action plan Set up,” Energy Economy Research, 4(2), 129-147, (2005)
23 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)   DOI   ScienceOn
24 K.I. Kingrey, Fuel Summary for Peach Bottom Unit 1 High- Temperature Gas-Cooled Reactor Cores 1 and 2, INEEL/ EXT-03-00103, (2003)
25 A. Shenoy, Gas Turbine Modular Helium Reactor (GT-MHR) Conceptual Design Description Report, GA report 910720, (1996)
26 D. Zhong and Y. Xu, Progress of the HTR-10 project, IAEATECDOC- 899, (1995)
27 K. Weaver, et.al, NGNP Preliminary Project Management Plan, INL/EXT-05-00952, (2006)
28 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)   DOI   ScienceOn
29 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)
30 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)   DOI
31 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)
32 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)
33 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)