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Research Articles

Simulating Properties of Canadian Research Reactor Fuels Important to Disposal

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Pages 1131-1154 | Received 13 Apr 2023, Accepted 20 Jun 2023, Published online: 03 Aug 2023

References

  • “Research Reactor Database (RRB),” International Atomic Energy Agency; https://nucleus.iaea.org/rrdb/ (accessed May 19, 2023).
  • “Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management,” Report CC172-23E-PDF, Government of Canada, Ottawa, Canada (2020).
  • “Postclosure Safety Assessment of a Used Fuel Repository in Sedimentary Rock,” Report NWMO-TR-2018-08, Nuclear Waste Management Organization, Toronto, Canada (2018).
  • J. W. HILBORN et al., “SLOWPOKE of the University of Toronto: A Laboratory Reactor for Neutron Irradiation,” Report AECL-4212, Atomic Energy of Canada Limited, Chalk River, Canada (1972).
  • K. M. WASYWICH, “Characteristics of Used CANDU Fuel Relevant to the Canadian Nuclear Fuel Waste Management Program,” Report AECL-10463, Atomic Energy of Canada Limited, Pinawa, Canada (1993).
  • “Waste Management, Volume III: Safety Case for the Disposal of Radioactive Waste,” Regulatory Document REGDOC-2.11.1 Volume III, Version 2, Canadian Nuclear Safety Commission, Ottawa, Canada (2021).
  • T. REILLY, “Nuclear Fuel Waste Projections in Canada—2022 Update,” Report NWMO-TR-2022-17, Nuclear Waste Management Organization, Toronto, Canada (2022).
  • B. A. HILTON, “Review of Oxidation Rates of DOE Spent Nuclear Fuel: Part 1: Metallic Fuel,” ANL-00/24, Argonne National Laboratory (2000).
  • C. SHELTON-DAVIS, “Review of DOE Spent Nuclear Fuel Release Rate Test Results,” DOE/SNF/REP-073, Idaho National Engineering and Environmental Laboratory (2003).
  • G. DEISSMANN et al., “Corrosion Behaviours of Spent Research Reactor Fuel Under OPERA Repository Conditions,” OPERA-PU-IBR551B, Onderzoeks Programma Eindberging Radioactief Afval, Nieuwdorp, Netherlands (2016).
  • H. CURTIUS et al., “Radionuclide Release from Research Reactor Spent Fuel,” J. Nucl. Mater., 416, 211 (2011); https://doi.org/10.1016/j.jnucmat.2010.12.221.
  • C. W. SOLBRIG, J. R. KRSUL, and D. N. OLSEN, “Pyrophoricity of Uranium in Long-Term Storage Environments,” ANL/TD-CP-84441, Argonne National Laboratory (1994).
  • M. J. BRADLEY and L. M. FERRIS, “Hydrolysis of Uranium Carbides Between 25 and 100°C, Part 1: Uranium Monocarbide,” Inorg. Chem., 1, 683 (1962); https://doi.org/10.1021/ic50015a029.
  • G. R. CASKEY, “Materials Issues in Interim Storage and Direct Disposal of Aluminum Clad Spent Nuclear Fuel,” WSRC-TR-93-502, Westinghouse Savannah River Company, Aiken, South Carolina (1993).
  • D. G. TURNER, “The WR-1 Reactor: A General Description,” Report AECL-4763, Atomic Energy of Canada Limited, Pinawa, Canada (1974).
  • M. A. FERADAY, “Fuels for Canadian Research Reactors,” Proc. 1978 Int. Mtg. on Reduced Enrichment for Research and Test Reactors (RERTR), Argonne National Laboratory, November 9–10, 1978.
  • K. HECKMAN and J. EDWARD, “Radionuclide Inventories for Reference CANDU Fuel Bundles,” Report NWMO-TR-2020-05, Nuclear Waste Management Organization, Toronto, Canada (2020).
  • I. C. TAIT, I. C. GAULD, and G. B. WILKIN, “Derivation of Initial Radionuclide Inventories for the Safety Assessment of the Disposal of Used CANDU Fuel,” Report AECL-9881, Atomic Energy of Canada Limited, Pinawa, Canada (1989).
  • E. A. G. LARSON, “A General Description of the NRX Reactor,” Report AECL-1377, Atomic Energy of Canada Limited, Chalk River, Canada (1961).
  • T. C. LEUNG, “Validation of Fuel Burnup for the NRU Research Reactor,” Proc. American Nuclear Society Winter Mtg., Washington, District of Columbia, November 10–14, 2013.
  • M. TAYAL and M. GACESA, “Storage and Disposal of Irradiated Fuel,” in Essential CANDU, Chap. 19, W. J. GARLAND., Ed., University Network of Excellence in Nuclear Engineering (2017).
  • S. SUNDER and D. W. SHOESMITH, “Chemistry of UO2 Fuel Dissolution in Relation to the Disposal of Used Nuclear Fuel,” Report AECL-10395, Atomic Energy of Canada Limited, Pinawa, Canada (1991).
  • P. SMITH, “Decay Heat Calculations for the Dalhousie University SLOWPOKE-2 Reactor (DUSR),” Memorandum SLWPK2-03320-220-000, Atomic Energy of Canada Limited, Chalk River, Canada (Apr. 13, 2010).
  • “Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada: Appendix A—Inventory and Characteristics of Spent Nuclear Fuel and High-Level Radioactive Waste and Other Materials,” DOE/EIS-0250, U.S. Department of Energy (2002).
  • J. PENCER et al., “Implications of Alpha-Decay for Long Term Storage of Advanced Heavy Water Reactor Fuels,” Ann. Nucl. Energy, 110, 400 (2017); https://doi.org/10.1016/j.anucene.2017.06.060.
  • W. A. WIESELQUIST, R. A. LEFEBVRE, and M. A. JESSEE, “SCALE Code System,” ORNL/TM-2005/39 Version 6.2.4, Oak Ridge National Laboratory (2020).
  • D. F. SEARS, M. D. ATFIELD, and I. C. KENNEDY, “The Conversion of NRU from HEU to LEU Fuel,” Proc. Int. Symp. on Research Reactor Safety Operations and Modifications, Chalk River, Canada, October 23–27, 1989.
  • G. KENNEDY et al., “LEU-Fueled SLOWPOKE-2 Research Reactors: Operational Experience and Utilization,” Proc. 2002 Int. Mtg. on Reduced Enrichment for Research and Test Reactors (RERTR), Bariloche, Argentina, November 3–8, 2002.
  • R. F. LIDSTONE, “The Evolution of Canadian Research Reactors: 1942 to 1992,” Report AECL-10760, Atomic Energy of Canada Limited, Pinawa, Canada (1993).
  • F. PUIG and H. DENNIS, “SLOWPOKE-2 Alternative Core Loading Configurations Analysis for Highly Improved Reactor Performance,” Ann. Nucl. Energy, 128, 216 (2019); https://doi.org/10.1016/j.anucene.2018.12.016.
  • W. A. WIESELQUIST and B. R. BETZLER, “SCALE 6.2.4 Validation: Overview,” ORNL/TM-2020/1500/v1, Oak Ridge National Laboratory (2022).
  • M. B. CHADWICK et al., “ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data,” Nucl. Data Sheets, 112, 12, 2887 (2011); https://doi.org/10.1016/j.nds.2011.11.002.
  • K. LIBERDA et al., “Elemental Composition of Unirradiated CANDU Fuel,” Proc. 14th Int. Conf. on CANDU Fuel, Mississauga, Canada, July 21–24, 2019.
  • L. WILK, “CANDU Fuel Burnup and Power Rating 2012 Update,” Report NWMO-TR-2013-02, Nuclear Waste Management Organization, Toronto, Canada (2013).

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