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Science and Technology of Nuclear Installations
Volume 2018, Article ID 5327146, 17 pages
https://doi.org/10.1155/2018/5327146
Research Article

Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors

McMaster University, Hamilton, ON, Canada

Correspondence should be addressed to David Novog; ac.retsamcm@govon

Received 29 August 2017; Revised 28 November 2017; Accepted 10 December 2017; Published 1 March 2018

Academic Editor: Tomasz Kozlowski

Copyright © 2018 Simon Younan and David Novog. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. International Atomic Energy Agency, Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors, International Atomic Energy Agency, Vienna, Austria.
  2. L. Haacke, Principles of Nuclear Safety, Course 4.3, Module 03 - Defence in Depth, CANTEACH, 1996.
  3. J. C. Luxat, “Thermal-hydraulic aspects of progression to severe accidents in CANDU reactors,” Nuclear Technology, vol. 167, no. 1, pp. 187–210, 2009. View at Publisher · View at Google Scholar · View at Scopus
  4. A. Labib and M. J. Harris, “Learning how to learn from failures: The Fukushima nuclear disaster,” Engineering Failure Analysis, vol. 47, pp. 117–128, 2015. View at Publisher · View at Google Scholar · View at Scopus
  5. E. J. Lahoda, L. Hallstadius, F. Boylan, and S. Ray, “What should be the objective of accident tolerant fuel?” in Proceedings of the 2014 Annual Meeting on Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014, pp. 733–736, usa, June 2014. View at Scopus
  6. D. Permar, A. Cartas, and H. Wang, “Innovative accident tolerant UO2 composite fuel for use in LWRs,” in Proceedings of the 2013 Winter Meeting on Transactions and Embedded Topical Meetings: Risk Management for Complex Socio-Technical Systems, 2nd ANS SMR 2013 Conference, Nuclear Nonproliferation - 1st Fission to the Future, pp. 185-186, usa, November 2013. View at Scopus
  7. D. Permar, Z. Chen, and J. Tulenko, “Enhanced accident tolerant UO2-diamond composite fuel pellets prepared by SPS,” in Proceedings of the 2013 Winter Meeting on Transactions and Embedded Topical Meetings: Risk Management for Complex Socio-Technical Systems, 2nd ANS SMR 2013 Conference, Nuclear Nonproliferation - 1st Fission to the Future, pp. 267–269, usa, November 2013. View at Scopus
  8. K. Y. Spencer, L. Sudderth, R. A. Brito et al., “Sensitivity study for accident tolerant fuels: Property comparisons and behavior simulations in a simplified PWR to enable ATF development and design,” Nuclear Engineering and Design, vol. 309, pp. 197–212, 2016. View at Publisher · View at Google Scholar · View at Scopus
  9. P. Malkki, “The manufacturing of uranium nitride for possible use in light water reactors,” 2015.
  10. J. J. Powers, W. J. Lee, F. Venneri et al., “Fully Ceramic Microencapsulated (FCM) Replacement Fuel for LWRs,” Tech. Rep. ORNL/TM-2013/173, 2013. View at Publisher · View at Google Scholar
  11. L. H. Ortega, J. Evans, and S. M. McDeavitt, “Development of a high density uranium nitride-uranium silicide composite accident tolerant fuel,” in Proceedings of the 2014 Annual Meeting on Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014, pp. 999-1000, usa, June 2014. View at Scopus
  12. J. M. Harp, P. A. Lessing, and R. E. Hoggan, “Uranium silicide fabrication for use in LWR accident tolerant fuel,” in Proceedings of the 2014 Annual Meeting on Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014, pp. 990–993, usa, June 2014. View at Scopus
  13. J. Creasy, “Thermal Properties of Uranium-Molybdenum Alloys: Phase Decomposition Effects of Heat Treatments,” 2011.
  14. R. A. Brown, C. Blahnik, and A. P. Muzumdar, “DEGRADED COOLING IN A CANDU REACTOR.,” Nuclear Science and Engineering, vol. 88, no. 3, pp. 425–435, 1984. View at Publisher · View at Google Scholar · View at Scopus
  15. G. J. Youinou and R. S. Sen, “Impact of accident-tolerant fuels and claddings on the overall fuel cycle: A preliminary systems analysis,” Nuclear Technology, vol. 188, no. 2, pp. 123–138, 2014. View at Publisher · View at Google Scholar · View at Scopus
  16. D. Burkes, G. Mickum, and D. Wachs, Thermophysical Properties of U-10Mo Alloy, 2010.
  17. J.-H. Chun, S.-W. Lim, B.-D. Chung, and W.-J. Lee, “Safety evaluation of accident-tolerant FCM fueled core with SiC-coated zircalloy cladding for design-basis-accidents and beyond DBAs,” Nuclear Engineering and Design, vol. 289, pp. 287–295, 2015. View at Publisher · View at Google Scholar · View at Scopus
  18. L. J. Ott, K. R. Robb, and D. Wang, “Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions,” Journal of Nuclear Materials, vol. 448, no. 1–3, pp. 520–533, 2014. View at Publisher · View at Google Scholar · View at Scopus
  19. B. Cheng, Y.-J. Kim, and P. Chou, “Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding,” Nuclear Engineering and Technology, vol. 48, no. 1, pp. 16–25, 2016. View at Publisher · View at Google Scholar · View at Scopus
  20. X. Wu, T. Kozlowski, and J. D. Hales, “Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions,” Annals of Nuclear Energy, vol. 85, pp. 763–775, 2015. View at Publisher · View at Google Scholar · View at Scopus
  21. C. P. Deck, G. M. Jacobsen, J. Sheeder et al., “Characterization of SiC-SiC composites for accident tolerant fuel cladding,” Journal of Nuclear Materials, vol. 466, pp. 1–15, 2015. View at Publisher · View at Google Scholar · View at Scopus
  22. X. Wu, P. Sabharwall, and J. Hales, “Neutronics and Fuel Performance Evaluation of Accident Tolerant Fuel under Normal Operation Conditions,” Tech. Rep. INL/EXT-14-32591, 2014. View at Publisher · View at Google Scholar
  23. N. M. George, K. Terrani, J. Powers, A. Worrall, and I. Maldonado, “Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors,” Annals of Nuclear Energy, vol. 75, pp. 703–712, 2015. View at Publisher · View at Google Scholar · View at Scopus
  24. J. M. Harp, P. A. Lessing, and R. E. Hoggan, “Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation,” Journal of Nuclear Materials, vol. 466, pp. 1–11, 2015. View at Publisher · View at Google Scholar · View at Scopus
  25. K. D. Johnson, A. M. Raftery, D. A. Lopes, and J. Wallenius, “Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications,” Journal of Nuclear Materials, vol. 477, pp. 18–23, 2016. View at Publisher · View at Google Scholar · View at Scopus
  26. J. Leppänen, “PSG2/Serpent a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code,” Tech. Rep., VTT Technical Research Centre of Finland, 2009. View at Google Scholar
  27. PDE Solutions Inc, FlexPDE 6 Version 6.40, PDE Solutions Inc., 2016.
  28. T. L. Rucker and C. M. Johnson, “Relationship between isotopic uranium activities and total uranium at various uranium enrichments,” Journal of Radioanalytical and Nuclear Chemistry, vol. 235, no. 1-2, pp. 47–52, 1997. View at Publisher · View at Google Scholar
  29. B. Becker, R. Dagan, and G. Lohnert, “Proof and implementation of the stochastic formula for ideal gas, energy dependent scattering kernel,” Annals of Nuclear Energy, vol. 36, no. 4, pp. 470–474, 2009. View at Publisher · View at Google Scholar · View at Scopus
  30. S. C. Cheng and R. I. Vachon, “The prediction of the thermal conductivity of two and three phase solid heterogeneous mixtures,” International Journal of Heat and Mass Transfer, vol. 12, no. 3, pp. 249–264, 1969. View at Publisher · View at Google Scholar · View at Scopus
  31. F. J. Doria, CANDU Safety #16: Large Loss-of-Coolant Accident with Coincident Loss of Emergency Core Cooling, Atomic Energy of Canada Limited, 2001.
  32. “Wolfram|Alpha curated data,” 2016.
  33. E. W. Lemmon, M. L. Huber, and M. O. McLinden, NIST Standard Reference Database 23: Reference Fluid Thermodynamic and Transport Properties-REFPROP, Version 9.1, Gaithersburg, Maryland, 2013.
  34. R. S. Hart and R. A. Olmstead, CANDU Passive Shutdown Systems, AECL CANDU, Mississauga, Ontario, Canada.