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Effect of DUPIC Cycle on CANDU Reactor Safety Parameters

  • Mohamed, Nader M.A. (Atomic Energy Authority) ;
  • Badawi, Alya (Department of Nuclear and Radiation Engineering, Alexandria University)
  • Received : 2016.01.05
  • Accepted : 2016.03.21
  • Published : 2016.10.25

Abstract

Although, the direct use of spent pressurized water reactor (PWR) fuel in CANda Deuterium Uranium (CANDU) reactors (DUPIC) cycle is still under investigation, DUPIC cycle is a promising method for uranium utilization improvement, for reduction of high level nuclear waste, and for high degree of proliferation resistance. This paper focuses on the effect of DUPIC cycle on CANDU reactor safety parameters. MCNP6 was used for lattice cell simulation of a typical 3,411 MWth PWR fueled by $UO_2$ enriched to 4.5w/o U-235 to calculate the spent fuel inventories after a burnup of 51.7 MWd/kgU. The code was also used to simulate the lattice cell of CANDU-6 reactor fueled with spent fuel after its fabrication into the standard 37-element fuel bundle. It is assumed a 5-year cooling time between the spent fuel discharges from the PWR to the loading into the CANDU-6. The simulation was carried out to calculate the burnup and the effect of DUPIC fuel on: (1) the power distribution amongst the fuel elements of the bundle; (2) the coolant void reactivity; and (3) the reactor point-kinetics parameters.

Keywords

References

  1. M.S. Yang, H. Choi, C.J. Jeong, K.C. Song, J.W. Lee, G.I. Park, H.D. Kim, W.I. Ko, J.J. Park, K.H. Kim, H.H. Lee, J.H. Park, The status and prospect of DUPIC fuel technology, Nucl. Eng. Technol. 38 (2006) 259-264.
  2. X. Zhonsheng, P.G. Boczar, CANDU Fuel-Cycle Vision [Internet]. 2015. Available from: http://www.nuceng.ca/canteachmirror/library/20054415.pdf.
  3. J.S. Lee, K.C. Song, M.S. Yang, K.S. Chun, B.W. Rhee, J.S. Hong, H.S. Park, C.S. Rim, H. Keil, Research and Development Program of KAERI for DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors), in: Proc. Int. Conf. Technology Exhibition Future Nuclear Systems Emerging Fuel Cycles and Waste Disposal Options (GLOBAL'93), Vol. 2, American Nuclear Society, Seattle, Washington, Sep 12-17, 1993, p. 733.
  4. J. Kang, A. Suzuki, Analysis on DUPIC fuel cycle in aspect of overall radioactive waste management, J. Nucl. Fuel Cycle Environ. 4 (1997-1998) 19-27. https://doi.org/10.3327/jnuce.4.19
  5. X. Zhao, M.J. Driscoll, M.S. Kazimi, Results of Spent Fuel in PWRs via Dry Processing, 7th International Conference on Nuclear Engineering, JSMA, Tokyo, Japan, Apr 19-23, 1999.
  6. C.A. Bollmann, Optimization of DUPIC, Cycle Environmental and Economic Performance, Massachusetts Institute of Technology, Cambridge, MA, 1998.
  7. N.M.A. Mohamed, Direct reuse of spent nuclear fuel, Nucl. Eng. Des. 278 (2014) 182-189. https://doi.org/10.1016/j.nucengdes.2014.07.017
  8. N.M.A. Mohamed, Design of a PWR for long cycle and direct recycling of spent fuel, Nucl. Eng. Des. 295 (2015) 259-566.
  9. J.W. Lee, G.I. Park, Y. Choi, Fabrication of DUPIC fuel pellets using high burn-up spent PWR fuel, J. Nucl. Sci. Technol. 49 (11) (2012) 1092-1096. https://doi.org/10.1080/00223131.2012.730898
  10. C.J. Jeong, H. Choi, Compatibility analysis on existing reactivity devices in CANDU 6 reactors for DUPIC fuel cycle, Nucl. Sci. Eng. 134 (2000) 265-280. https://doi.org/10.13182/NSE00-A2115
  11. O. Michaela, Assessment Document, ACR-700 Reactor Physics Design, 1 0810-03300-ASD-001, Revision 2, Atomic Energy of Canada Limited, Ontario, Canada, 2003.
  12. J.V. Marczak, Low Enriched Uranium Fuel Cycle in Heavy Water Reactors, McMaster University, Hamilton, ON, 1990.
  13. J.R. Lamarch, Introduction to Nuclear Engineering, Addison-Wesley Publishing Company, Inc, USA, 1983.
  14. C.W. Lau, Improved PWR Core Characteristics with Thorium-containing Fuel, Chalmers University of Technology, Gothenburg, Sweden, 2014.
  15. K. Almenas, R. Lee, Nuclear Engineering: An Introduction, Springer-Verlag, Berlin Heidelberg, 1992.
  16. D.B. Pelowitz, $MCNP6^{TM}$ User's Manual Version 1.0, LA-CP-13-00634, Rev. 0, Los Alamos National Security, LLC, Los Alamos, NM, 2013.
  17. W.B. Wilson, T.R. England, D.C. George, P.G. Young, Recent Development of the CINDER90 Transmutation Code and Data Library for Actinide Transmutation Studies, Los Alamos National Laboratory, Los Alamos, NM, 1995.
  18. W.M. Stacey, Nuclear Reactor Physics, John Wiley & Sons, Inc., New York, 2001.