Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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DYNAMIC MODELING AND ANALYSIS OF ALTERNATIVE FUEL CYCLE SCENARIOS IN KOREA

  • Published : 2007.02.28
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Abstract

The Korean nuclear fuel cycle was modeled by the dynamic analysis method, which was applied to the once-through and alternative fuel cycles. First, the once-through fuel cycle was analyzed based on the Korean nuclear power plant construction plan up to 2015 and a postulated nuclear demand growth rate of zero after 2015. Second, alternative fuel cycles including the direct use of spent pressurized water reactor fuel in Canada deuterium uranium reactors (DUPIC), a sodium-cooled fast reactor and an accelerator driven system were assessed and the results were compared with those of the once-through fuel cycle. The once-through fuel cycle calculation showed that the nuclear power demand would be 25 GWe and the amount of the spent fuel will be ${\sim}65000$ tons by 2100. The alternative fuel cycle analyses showed that the spent fuel inventory could be reduced by more than 30% and 90% through the DUPIC and fast reactor fuel cycles, respectively, when compared with the once-through fuel cycle. The results of this study indicate that both spent fuel and uranium resources can be effectively managed if alternative reactor systems are timely implemented along with the existing reactors.

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References

  1. 'Report to Congress on Advanced Fuel Cycle Initiative: The Future Path for Advanced Spent Fuel Treatment and Transmutation Research,' U.S. Department of Energy, Office of Nuclear Energy, Science and Technology, 2003
  2. 'A Technology Roadmap for Generation IV Nuclear Energy Systems,' U.S. Department of Energy GIF- 002-00, 2002
  3. J.S. Lee, K.C. Song, M.S. Yang, K.S. Chun, J.S. Hong, H.S. Park and H. Keil, 'Research and Development Program of KAERI for DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors),' Proc. Int. Conf. on Future Nuclear System: Emerging Fuel Cycles and Waste Disposal Options (Global'93), Seattle, USA, Sept. 12-17, 1993
  4. M.S. Yang, Y.W. Lee, K.K. Bae and S.H. Na, 'Conceptual Study on the DUPIC Fuel Manufacturing Technology,' Proc. Int. Conf. on Future Nuclear System: Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Seattle, USA, Sept. 12-17, 1993
  5. H. Song, S.J. Kim and Y.I. Kim, 'Nuclear Design of a Na Cooled KALIMER-600 Core with no Blanket,' Advances in Nuclear Fuel Management III, Hilton Head Island, USA, Oct. 5-8, 2003
  6. S.G. Hong, Y. S. Shim, Y.I Kim, Y.G. Kim, B. W. Lee, H. Song, K.B. Lee, J.W. Jang and D.U. Lee, 'Current Status of the Transmutation Reactor Technology and Preliminary Evaluation of Transmutation Performance of the KALIMER Core,' KAERI/TR- 3068/2005, Korea Atomic Energy Research Institute, 2005
  7. Y. Kim, W.S. Park, T.Y. Song and C.K. Park, 'Optimization of Height-to-Diameter Ratio for an Accelerator-Driven System,' Nuclear Science and Engineering, 143, 141, 2002
  8. Y. Kim, W.S. Park and R.N. Hill, 'Core Design Characteristics of the HYPER System,' OECD/NEA 7th Information Exchange Meeting on Actinide and Fission Product Partitioning & Transmutation, Jeju, Korea, Oct. 14-16, 2002
  9. 'Generation 4 Roadmap Fuel Cycle Crosscut Group Executive Summary,' U.S. Department of Energy, Nuclear Energy Research Advisory Committee and the Generation IV International Forum, 2001
  10. J.H. Park, C.J. Jeong and H. Choi, 'Implementation of a Dry Process Fuel Cycle Model into the DYMOND Code,' J. Korean Nuclear Society, 36, 175, 2004
  11. B. Richmond, An Introduction to Systems Thinking, High Performance System Inc., Lebanon, New Hampshire, 2001
  12. National Research Council, 'Nuclear Waste: Technologies for Separation and Transmutation,' National Academy Press, Washington D.C., 1996
  13. E.D. Collins, D.E. Benker, B.B. Spencer, P. Baron, B. Dinh, W.D. Bond and D.O. Campbell, 'Development of the UREX+ Co-Decontamination Solvent Extraction Process,' Proc. GLOBAL 2003, New Orleans, USA, Nov. 16-20, 2003
  14. E.J. Karell, K.V. Gourishankar, J.L. Smith, L.S. Chow and L. Redey, 'Separation of Actinides from LWR Spent Fuel Using Molten-Salt-Based Electrochemical Processes,' Nuclear Technology, 136, 342, 2001
  15. T. Inoue, 'Actinide Recycling by Pyro-Process with Metal Fuel FBR for Future Nuclear Fuel Cycle System,' Progress in Nuclear Energy, 40, 547, 2002 https://doi.org/10.1016/S0149-1970(02)00049-5
  16. 'The Second Basic Electricity Demand and Supply Plan,' Ministry of Commerce, Industry and Energy, 2004
  17. S.S. Witter, D.C. Krupp, F.A. Monger, R.E. Radcliffe, R.A. Churchin and J.M. Byrne, 'The Nuclear Design and Core Physics Characteristics of the Korea Nuclear Units 7 and 8 Cycle 1,' WCAP-10803, Westinghouse Electric Corporation, 1985
  18. 'Design Manual: CANDU 6 Generating Station Physics Design Manual,' 86-03310-DM000, Rev. 1, Atomic Energy of Canada Limited, 1995
  19. 'Yucca Mountain Science and Engineering,' DOE/ RW-0539, US Department of Energy, 2001
  20. D.C. Wade and Y.I. Chang, 'The Integral Fast Reactor Concept: Physics of Operation and Safety,' Nuclear Science and Engineering, 100, 507, 1988

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