DOI QR코드

DOI QR Code

Nuclear waste attributes of near-term deployable small modular reactors

  • Taek K. Kim (Argonne National Laboratory) ;
  • L. Boing (Argonne National Laboratory) ;
  • B. Dixon (Idaho National Laboratory)
  • Received : 2023.06.25
  • Accepted : 2024.01.28
  • Published : 2024.03.25

Abstract

The nuclear waste attributes of near-term deployable SMRs were assessed using established nuclear waste metrics, which are the DU mass, SNF mass, volume, activity, decay heat, radiotoxicity, and decommissioning LLW volumes. Metrics normalized per unit electricity generation were compared to a reference large PWR. Three SMRs, VOYGR, Natrium, and Xe-100, were selected because they represent a range of reactor and fuel technologies and are active designs deployable by the decade's end. The SMR nuclear waste attributes show both some similarities to the PWR and some significant differences caused by reactor-specific design features. The DU mass is equivalent to or slightly higher than the PWR. Back-end waste attributes for SNF disposition vary, but the differences have a limited impact on long-term repository isolation. SMR designs can vary significantly in SNF volume (and thus heat generation density). However, these differences are amenable to design optimization for handling, storage, transportation, and disposal technologies. Nuclear waste attributes from decommissioning vary depending on design and decommissioning technology choices. Given the analysis results in this study and assuming appropriate waste management system and operational optimization, there appear to be no major challenges to managing SMR nuclear wastes compared to the reference PWR.

Keywords

Acknowledgement

This work was funded by the Systems Analysis and Integral Campaign of the Office of Nuclear Fuel Cycle and Supply Chain, U.S. Department of Energy's Office of Nuclear Energy. This manuscript has been created by UChicago Argonne, LLC, Operator of Argonne National Laboratory ("Argonne"), and Battelle Energy Alliance, LLC, Operator of Idaho National Laboratory, under Contract No. DE-AC07-05ID14517 with the U.S. Department of Energy (DOE).

References

  1. "Nuclear Fuel Cycle Evaluation and Screening - Final Report, Appendix C," FCRDFCO-2014-000106, Idaho National Laboratory, October 2014.
  2. NRC to issue rule certifying NuScale design, Nuclear Newswire, American Nuclear Society (Aug. 1, 2022).
  3. J. Reyes, Correction of Factual Error in PNAS Paper titled "Nuclear waste from small modular reactors, Letter to PNAS Editor-in-Chief (May 31, 2020).
  4. Carbon Free Power Project," NuScale Power LLC, https://www.nuscalepower.com/projects/carbon-free-power-project.
  5. "Overview of Design Optimization Process for a Commercial Nuclear Core," Public Access Records Office, National Academy of Science https://www.nationalacademies.org/our-work/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors.
  6. U.S. Department of Energy Announces $160 Million in First Awards under Advanced Reactor Demonstration Program, U.S. Department of Energy Office of Nuclear Energy, Oct. 13, 2020.
  7. T. Neider, Natrium, Presentation to National Academies of Sciences, Engineering, and Medicine (Feb. 2, 2021).
  8. TerraPower and PacifiCorp announce efforts to expand Natrium technology deployment, Terra (October 27, 2022).
  9. R.I. Smith, G.J. Konzek, W.E. Kennedy, "Technology, Safety and Costs of Decommissioning a Reference Pressurized Water Reactor Power Station," NUREG/ CR-0130, U.S. Nuclear Regulatory Commission, 1978.
  10. G.J. Konzek, et al., "Revised Analyses of Decommissioning for the Reference Pressurized Water Reactor Power Station," NUREG/CR-5884, PNL-8742, U.S. Nuclear Regulatory Commission, 1995.
  11. Issued Combined Licenses and Limited Work Authorizations for Vogtle, Units 3 and 4, U.S. Nuclear Regulatory Commission, 2020.
  12. A. Mancini, et al., Greater-Than-Class C Low-Level Nuclear Waste Characterization/Appendix A-3: Basis for Greater-Than-Class C Low-Level Nuclear Waste Light Water Reactor Projections, Idaho National Engineering Laboratory, September, 1994. DOE/LLW-114A-3.
  13. T. Neider, NATRIUM, Presentation to ANSWER, May 6, 2021.
  14. E.J. Mulder, W.A. Boyes, Neutronics characteristics of a 165 MWt Xe-100 reactor, Nucl. Eng. Des. 357 (2020) 110415.
  15. E.J. Mulder, Xe-100 High Level Considerations-ANSWER Working Group, Presentation to National Academy of Sciences, March 4, 2021.
  16. E.J. Mulder, X-Energy's Xe-100 Reactor Design Status, Presentation to National Academy of Sciences, May 26, 2021.
  17. E.J. Mulder, Overview of X-energy's 200 MWt Xe-100 reactor, Presentation to NUPIC Vendor Conference (June 2021).
  18. B.S. Triplett, PRISM: a Competitive small modular sodium-cooled reactor, Nucl. Technol. 178 (2) (2010) 186-200.
  19. "Pre-application Activities for Advanced Reactors," U.S. Nuclear Regulatory Commission, https://www.nrc.gov/reactors/new-reactors/advanced/licensing-activities/pre-application-activities/natrium.html.
  20. "Frequently Asked Questions about Depleted Uranium Deconversion Facilities," U. S. Nuclear Regulatory Commission, https://www.nrc.gov/materials/fuel-cyclefac/ur-deconversion/faq-depleted-ur-decon.html.
  21. K. Eckerman, et al., "Compendium of Dose Coefficients Based on ICRP Publication 60," ICRP Publication 119, The International Commission on Radiological Protection, 2012.
  22. "Greater-Than-Class C and Transuranic Waste," U.S. Nuclear Regulatory Commission, https://www.nrc.gov/waste/llw-disposal/llw-pa/gtcc-transuranicwaste-disposal.html.
  23. R. McGrath, R. Reid, "Waste management for decommissioning of nuclear power plants: an EPRI decommissioning Program report," symposium on recycling of metals arising from operation and decommissioning of nuclear facilities, Studsvik Facility (2014). Nykoping, Sweden, April 8-10.
  24. K. Lee, et al., "Preliminary evaluation of decommissioning wastes for the first commercial nuclear power reactor in South Korea," world academy of science, Engineering and Technology International Journal of Nuclear and Quantum Engineering 11 (2017) 615-621.
  25. T.K. Kim, L. Bowing, B. Dixon, Nuclear waste attributes of SMRs scheduled for near-term deployment, ANL/NSE-22/98, Revision 1 (Nov. 18, 2022).
  26. "How the NuScale Model Works," NuScale Power LLC, https://www.nuscalepower.com/technology/technology-overview.
  27. "NuScale Standard Plant Design Certification Application," Revision 5, NuScale Power LLC, July 2020.
  28. J.L. Minns, et al., "Staff Responses to Frequently Asked Questions Concerning Decommissioning of Nuclear Power Reactors," NUREG-1628, U.S. Nuclear Regulatory Commission, June 2020.
  29. W.F. Brehm, et al., "Corrosion and Fission Products in Primary Systems of Liquid Metal Cooled Reactors in the USA," HEDL-SA-3689 FP, Westinghouse Hanford Company and Argonne National Laboratory-West; IAEA/IWGFR Specialists' Meeting on Fission and Corrosion Products in Primary System of LMFBRs, May 1987.
  30. J.A. Michelbacher, et al., "The Sodium Process Facility at Argonne National Laboratory-West," Technical Committee Meeting on Sodium Removal and Disposal from LMFRs in Normal Operation and in the Framework of Decommissioning, Aix-En-Provence, 1997. France, November 3-7.
  31. R.W. Benedict, et al., Environmental - nuclear technology activities at Argonne national laboratory-west, WP-01 Conference (2001). February 25-March 1.
  32. N. Sakaba, et al., Short design descriptions of other systems of the HTTR, Nucl. Eng. Des. 233 (2004) 147-154.