National Academies Press: OpenBook
« Previous: 6 Nonproliferation Implications and Security Risks
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

References

10 CFR 20(E). “Radiological Criteria for License Termination,” U.S. Nuclear Regulatory Commission. https://www.nrc.gov/reading-rm/doc-collections/cfr/part020/part020-1401.html.

10 CFR 37. “Physical Protection of Category I and Category II Quantities of Radioactive Material,” U.S. Nuclear Regulatory Commission, https://www.nrc.gov/reading-rm/doc-collections/cfr/part037/index.html.

10 CFR 50. “Domestic Licensing of Production and Utilization Facilities,” U.S. Nuclear Regulatory Commission. https://www.nrc.gov/reading-rm/doc-collections/cfr/part050/index.html.

10 CFR 50.2. “Domestic Licensing of Production and Utilization Facilities: Definitions,” U.S. Nuclear Regulatory Commission. https://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-0002.html.

10 CFR 51.23. “Environmental impacts of continued storage of spent nuclear fuel beyond the licensed life for operation of a reactor.” U.S. Nuclear Regulatory Commission. https://www.nrc.gov/reading-rm/doc-collections/cfr/part051/full-text.html#part051-0023.

10 CFR 71. “Packaging and Transportation of Radioactive Material,” U.S. Nuclear Regulatory Commission. https://www.nrc.gov/reading-rm/doc-collections/cfr/part071/index.html.

10 CFR 71.5. “Transportation of Licensed Material,” U.S. Nuclear Regulatory Commission, https://www.nrc.gov/reading-rm/doc-collections/cfr/part071/part071-0005.html.

10 CFR 71.55. “General Requirements for Fissile Material Packages,” U.S. Nuclear Regulatory Commission. https://www.nrc.gov/reading-rm/doc-collections/cfr/part071/part071-0055.html.

10 CFR 72. “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste,” U.S. Nuclear Regulatory Commission. https://www.nrc.gov/reading-rm/doc-collections/cfr/part072/full-text.html.

10 CFR 73. “Physical Protection of Plants and Materials,” U.S. Nuclear Regulatory Commission, https://www.nrc.gov/reading-rm/doc-collections/cfr/part073/full-text.html.

10 CFR 74.53. “Process Monitoring,” U.S. Nuclear Regulatory Commission. https://www.nrc.gov/reading-rm/doc-collections/cfr/part074/full-text.html#part074-0053.

40 CFR 190. “Environmental Radiation Protection Standards for Nuclear Power Operations,” U.S. Environmental Protection Agency. https://www.ecfr.gov/current/title-40/chapter-I/subchapter-F/part-190.

49 CFR 172, Subpart I, “Safety and Security Plans,” U.S. Department of Transportation. https://www.ecfr.gov/current/title-49/subtitle-B/chapter-I/subchapter-C/part-172/subpart-I.

49 CFR 173. “Shippers—General Requirements for Shipments and Packagings,” U.S. Department of Transportation. https://www.ecfr.gov/current/title-49/subtitle-B/chapter-I/subchapter-C/part-173.

49 CFR 173.420, “Uranium hexafluoride (fissile, fissile excepted, and non-fissile),” U.S. Department of Transportation. https://www.ecfr.gov/current/title-49/subtitle-B/chapter-I/subchapter-C/part-173#173.420.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Adams, R. 2021. China’s high temperature reactor—pebble bed modular (HTR-PM) achieves first criticality. Atomic Insights (September 14). https://atomicinsights.com/chinas-high-temperature-reactor-pebble-bed-modular-htr-pm-achieves-its-first-criticality.

Ainger, J. 2022. “EU Lawmakers Remove Last Hurdle to Label Gas, Nuclear as Green.” Bloomberg. July 6, 2022. https://www.bloomberg.com/news/articles/2022-07-06/eu-lawmakers-remove-last-hurdle-for-gas-nuclear-as-green.

AIP (American Institute of Physics). 2021. “FY22 Budget Outlook: DOE Applied Energy R&D.” FYI Science Policy News 78(August 26). https://www.aip.org/fyi/2021/fy22-budget-outlook-doe-applied-energy-rdd.

Aitkaliyeva, A., M. Tonks, J. Hirschhorn, J. Powers, I. Greenquist, and B. Beeler. 2020. “Research Needs for Uranium-Zirconium- Based Metallic Fuels.” Idaho Falls, ID: Idaho National Laboratory, June 1. https://doi.org/10.2172/1634988.

Ancius, D., V. Remeikis, A. Plukis, R. Plukiene, D. Ridikas, and M. Cometto. 2005. “Evaluation of the Activity of Irradiated Graphite in the Ignalina Nuclear Power Plant RBMK-1500 Reactor.” Nukleonika 50(3):113-120.

Andrews, A. 2008. “Nuclear Fuel Reprocessing: U.S. Policy Development.” Washington, DC: Congressional Research Service. March 27. https://sgp.fas.org/crs/nuke/RS22542.pdf.

ANDRA (Agence nationale pour la gestion des déchets radioactifs). 2006. “Inventaire National Des Déchets Radioactifs et Des Matières Valorisables.” Paris, France: Agence nationale pour la gestion des déchets radioactifs. https://inventaire.andra.fr/sites/default/files/documents/pdf/fr/in_-_edition_2006_-_rapport_de_synthese.pdf.

ANS. 2020. “BWXT Restarts TRISO Fuel Manufacturing.” NuclearNewswire, November 12. https://www.ans.org/news/article-2369/bwxt-restarts-triso-fuel-manufacturing.

Apted, M., J. Kessler, M. Kozak, M. Nutt, A. Orrell, A. Sowder, and P. Swift. 2012. “‘Radiotoxicity Index’: An Inappropriate Discriminator for Advanced Fuel Cycle Technology Selection.” In WM2012 Conference. Phoenix, AZ. https://www.osti.gov/servlets/purl/1078789.

Arcos, D., F. Grandia, C. Domènech, A. M. Fernández, M. V. Villar, A. Muurinen, T. Carlsson, P. Sellin, and P. Hernán. 2008. “Long-Term Geochemical Evolution of the near Field Repository: Insights from Reactive Transport Modelling and Experimental Evidences.” Radiogeochemical Aspects of Nuclear Waste Disposal 102(3):196-209 (December 12). https://doi.org/10.1016/j.jconhyd.2008.09.021.

Arm, S. T., D. E. Holcomb, R. L. Howard, and B. Riley. 2020. “Status of Fast Spectrum Molten Salt Reactor Waste Management Practice.” PNNL-30739 (December). Pacific Northwest National Laboratory. https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-30739.pdf.

Arostegui, D. A., and M. Holt. 2019. “Advanced Nuclear Reactors: Technology Overview and Current Issues.” Congressional Research Service. R45706. April 18. https://www.everycrsreport.com/files/20190418_R45706_86fb03d4ca6ab0e3f37bb71cfe23f44274a0ce84.pdf.

ARPA-E (Advanced Research Projects Agency–Energy). 2021. “Optimizing Nuclear Waste and Advanced Reactor Disposal Systems (ONWARDS),” Funding Opportunity Announcement, May 19, 2021.

Back, C., and R. Schleicher. 2021. “General Atomics Electromagnetic Systems.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, January 13, virtual meeting. https://www.nationalacademies.org/event/01-11-2021/merits-and-viability-of-different-nuclearfuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-january-11-2021-and-january-13-2021meeting.

Balakrishna, P. 2012. “ThO2 and (U, Th)O2 processing—A review,” Natural Science 4(Special Issue):943-949. http://dx.doi.org/10.4236/ns.2012.431123.

Ball, S. J., and S. E. Fisher. 2008. “Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs).” Prepared for U.S. Nuclear Regulatory Commission. Oak Ridge, TN: Oak Ridge National Laboratory. https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6944/v1/index.html.

Barber, G. 2022. “The Nuclear Reactors of the Future Have a Russia Problem.” Wired. March 17, 2022. https://www.wired.com/story/the-nuclear-reactors-of-the-future-have-a-russia-problem.

Bari, R., L-Y Cheng, J. Phillips, J. Pilat, G. Rochau, I. Therios, R. Wigeland, E. Wonder, and M. Zentner. 2009. “Proliferation Risk Reduction Study of Alternative Spent Fuel Processing.” Brookhaven National Laboratory. BNL-90264-2009-CP (July). https://www.bnl.gov/isd/documents/70289.pdf.

Baron, P., S. M. Cornet, E. D. Collins, G. DeAngelis, G. Del Cul, Yu. Fedorov, J. P. Glatz, V. Ignatiev, T. Inoue, A. Khaperskaya, I. T. Kim, M. Kormilitsyn, T. Koyama, J. D. Law, H. S. Lee, K. Minato, Y. Morita, J. Uhlíř, D. Warin, and R. J. Taylor. 2019. “A Review of Separation Processes Proposed for Advanced Fuel Cycles Based on Technology Readiness Level Assessments.” Progress in Nuclear Energy 117(November):103091. https://doi.org/10.1016/j.pnucene.2019.103091.

Barrasso, J. 2022. “Barrasso Leads Bill to Ban Russian Uranium Imports.” John Barrasso: United States Senator—Wyoming. March 17, 2022. https://www.barrasso.senate.gov/public/index.cfm/2022/3/barrasso-leads-bill-to-ban-russian-uranium-imports.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Bates, B. 2020. “HALEU Production at the Savannah River Site (SRS).” Presented at the HALEU Webinar, April 28, 2020. https://gain.inl.gov/HALEU_Webinar_Presentations/09-Bates,SRNL_Capabilities-28Apr2020.pdf.

Bathke, C. G. 2021. “Attractiveness of Materials in Advanced Nuclear Fuel Cycles.” LA-UR-21-25980. Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, July 20, virtual meeting. https://www.nationalacademies.org/event/07-20-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-8-july-20-2021.

Bathke, C. G., B. B. Ebbinghaus, B. A. Collins, B. W. Sleaford, K. R. Hase, M. Robel, R. K. Wallace, K. S. Bradley, J. R. Ireland, G. D. Jarvinen, M. W. Johnson, A. W. Prichard, and B. W. Smith. 2012. “The Attractiveness of Nuclear Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios.” Nuclear Technology 179(1):5-30. https://doi.org/10.13182/NT10-203.

Bays, S. E., G. A. Reyes, M. J. Schanfein, R. H. Stewart, and N. P. Martin. 2021. “Significant Quantity Production Rates in Small Modular Reactors.” INL/CON-21-63833-Revision 0 (August). Idaho National Laboratory.

Bělovský, L. 2019. “The ALLEGRO experimental gas-cooled fast reactor project.” Presentation to the Generation IV International Forum, March 20, webinar. https://www.gen-4.org/gif/jcms/c_105738/ladislav-belovsky-webinar-annoucement-final.

Berger, M. O. 2018. “The Nuclear Option: Technology to Extract Uranium From the Sea Advances.” The New Humanitarian, June 28, 2018. https://deeply.thenewhumanitarian.org/oceans/articles/2018/06/28/the-nuclear-option-technology-to-extract-uranium-from-the-sea-advances.

Bespala, E. V., M. V. Antonenko, D. O. Chubreev, A. V. Leonov, I. Yu Novoselov, A. P. Pavlenko, and V. N. Kotov. 2019. “Electrochemical Treatment of Irradiated Nuclear Graphite.” Journal of Nuclear Materials 526:151759. https://doi.org/10.1016/j.jnucmat.2019.151759.

Betti, M., L. Aldave de las Heras, A. Janssens, E. Henrich, G. Hunter, M. Gerchikov, M. Dutton, A. W. van Weers, S. Nielsen, J. Simmonds, A. Bexon, T. Sazykina. 2004. “Results of the European Commission Marina II Study Part II—Effects of Discharges of Naturally Occurring Radioactive Material.” Papers from the International Conference on Radioactivity in the Environment, Monaco, 1-5 September 2002 74(1):255-277. January 1. https://doi.org/10.1016/j.jenvrad.2004.01.021.

Bisplinghoff, B., M. Lochny, J. Fachinger, and H. Bruecher. 2000. “Radiochemical Characterization of Graphite from Juelich Experimental Reactor (AVR).” Nuclear Energy (1978) 39(5):311-315.

Bixler, N. E., F. Gelbard, D. L. Y. Louis, and J. Phillips. 2017. “Review of Spent Fuel Reprocessing and Associated Accident Phenomena.” NUREG/CR-7232. Albuquerque, NM: Sandia National Laboratory, February. https://www.nrc.gov/docs/ML1704/ML17045A577.pdf.

Black, G., and S. Peterson. 2018. “Economic Impact Report: Construction and Operation of a Small Modular Reactor Electric Power Generation Facility at the Idaho National Laboratory Site, Butte County, Idaho.” Regional Economic Development Organization for East Idaho. https://www.uidaho.edu/-/media/UIdaho-Responsive/Files/president/direct-reports/mcclure-center/Research-Reports/redi-economic-impact-report-pdf.pdf.

Black, G. A., F. Aydogan, and C. L. Koerner. 2019. “Economic Viability of Light Water Small Modular Nuclear Reactors: General Methodology and Vendor Data.” Renewable and Sustainable Energy Reviews 103(April):248-258. https://doi.org/10.1016/j.rser.2018.12.041.

Blandford, E., and P. Peterson. 2021. “Kairos Power.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors. January 13, virtual meeting. https://www.nationalacademies.org/event/01-11-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-january-11-2021-and-january-13-2021-meeting.

Boyer, B. 2021. “Proliferation Resistance Using Methodology of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO).” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors, September 14, virtual meeting. https://www.nationalacademies.org/event/09-13-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-9-september-13-15-2021.

BRC (Blue Ribbon Commission on America’s Nuclear Future). 2012. Report to the Secretary of Energy. January. U.S. Department of Energy. https://www.energy.gov/sites/prod/files/2013/04/f0/brc_finalreport_jan2012.pdf.

Breeder Reactor Corporation. 1985. Final Report: The Clinch River Breeder Reactor Plant Project. l98 160205 001. Breeder Reactor Corporation. https://www.nrc.gov/docs/ML1806/ML18064A893.pdf.

Brown, A., and A. Glaser. 2016. “On the Origins and Significance of the Limit Demarcating Low-Enriched Uranium from Highly Enriched Uranium.” Science and Global Security 24(2):131-137. https://doi.org/10.1080/08929882.2016.1184533.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Brown, N., Worrall, A., and Todosow, M. 2017. “Impact of Thermal Spectrum Small Modular Reactors on Performance of Once-through Nuclear Fuel Cycles with Low-Enriched Uranium.” Annals of Nuclear Energy 101(March):166-173. https://doi.org/10.1016/j.anucene.2016.11.003.

Bunn, M. 2021. “The Economics of Reprocessing and Recycling vs. Direct Disposal of Spent Nuclear Fuel.” Presented at the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors, online, June 7. https://www.nationalacademies.org/event/06-07-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-6-part-2-june-7-2021.

Bunn, M., Fetter, S., Holdren, J., and van der Zwaan, B. 2003. “The Economics of Reprocessing vs. Direct Disposal of Spent Nuclear Fuel.” DE-FG26-99FT4028. Project on Managing the Atom. Cambridge, MA: Harvard University. https://scholar.harvard.edu/files/matthew_bunn/files/bunn_the_economics_of_reprocessing_vs_direct_disposal_of_spent_nuclear_fuel.pdf.

Bushuev, A. V., V. N. Zubarev, and I.M. Proshin. 2002. “Composition and Content of Impurities in Graphite of Industrial Reactors” Radiation Protection Dosimetry 92(January 1):298-302.

Caponiti, A. 2020a. “Status of Advanced Reactor Demonstration Programs.” Presentation at the Gateway for Accelerated Innovation in Nuclear (GAIN) Workshop on HALEU, April 28, webinar. https://gain.inl.gov/HALEU_Webinar_Presentations/03-Caponiti,ARDP_Status_for_HALEU_Workshop,Rev1-28Apr2020.pdf.

Caponiti, A. 2020b. “Support for Advanced Reactor Development and Deployment.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 22, virtual meeting. https://www.nationalacademies.org/event/09-21-2020/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-september-21-23-2020-meeting.

Caponiti, A. 2022. Communication from Alice Caponiti, Deputy Assistant Secretary for Reactor Fleet and Advanced Reactor Deployment in the Office of Nuclear Energy, February 20, 2022.

Carbonnier, J.-L. 2006. “Merits of Fast Reactors for an efficient use of uranium ore and reduction of ultimate waste.” MIT Symposium: Rethinking the Nuclear Fuel Cycle, Cambridge, MA. October 30-31.

Carmack, W. J., S. L. Hayes, J. M. Harp, R. S. Fielding, S. A. Maloy, and T. A. Saleh. 2017. “Overview of the U.S. DOE Fast Reactor Fuel Development Program.” In International Conference on Fast Reactors and Related Fuel Cycles. Yekaterinburg, Russian Federation. https://media.superevent.com/documents/20170620/2c79371c8ad3f55aad0a98836c2a24fb/fr17-207.pdf.

Castelli, R., T. Gervais, D. Favet, and B. Ytournel. 2009. “COEXTM Pellet Fabrications in MELOX Test Chain.” In Proceedings of GLOBAL 2009. Paris, France, 2009.

CBO (Congressional Budget Office). 2007. “Costs of Reprocessing Versus Directly Disposing of Spent Fuel.” Testimony of Peter R. Orszag, Director, before the Senate Committee on Energy and Natural Resources. Washington, DC: Congressional Budget Office. November 14, 2007. https://www.cbo.gov/publication/19318.

CEA (Alternative Energies and Atomic Energy Commission). 2008. “Treatment and Recycling of Spent Nuclear Fuel: Actinide Partitioning—Application to Waste Management.” A Nuclear Energy Division Monograph. France: Alternative Energies and Atomic Energy Commission, 2008.

CEA. 2009. “Nuclear Waste Conditioning.” A Nuclear Energy Division Monograph. France: Alternative Energies and Atomic Energy Commission, 2009. https://www.cea.fr/english/Documents/scientific-and-economic-publications/nuclear-energy-monographs/CEA_Monograph5_Nuclear-waste-conditioning_2009_GB.pdf.

CEA. 2015. “Advances in Research on Partitioning and Transmutation and Plutonium Multi-Recycling in Fast Neutron Reactors,” Nuclear Energy Division, June 2015. https://www.cea.fr/english/Documents/corporate-publications/advances-research-on-partitioning-transmutation-and-plutonium-multi-recycling-in-fast-neutron-reactors.pdf.

CEA. n.d. “About the JHR.” Jules Horowitz Reactor. https://jhrreactor.com/en/about.

CGSR (Center for Global Security Research). 2000. “Proliferation-Resistant Nuclear Power Systems: A Workshop on New Ideas, June 2-4, 1999.” UCRL-JC-137954/CGSR-2000-001. Livermore, CA: Lawrence Livermore National Laboratory, March 2000. https://cgsr.llnl.gov/content/assets/docs/CGSR_2000_001.pdf.

Chiba, S., T. Wakabayashi, Y. Tachi, N. Takaki, A. Terashima, S. Okumura, and T. Yoshida. 2017. “Method to Reduce Long-Lived Fission Products by Nuclear Transmutations with Fast Spectrum Reactors.” Scientific Reports 7(1):13961. October 24. https://doi.org/10.1038/s41598-017-14319-7.

Choi, E.-Y., and S. M. Jeong. 2015. “Electrochemical Processing of Spent Nuclear Fuels: An Overview of Oxide Reduction in Pyroprocessing Technology.” Progress in Natural Science: Materials International 25(6):572-582. December 1. https://doi.org/10.1016/j.pnsc.2015.11.001.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Chung, K., D. Beddingfield, W. H.Geist, S.-Y. H. Lee, 2012. “Development of a Reliable Fuel Depletion Methodology for the HTR-10 Spent Fuel Analysis” LA-UR-12-22447. https://permalink.lanl.gov/object/tr?what=info:lanl-repo/lareport/LA-UR-12-22447.

Cipiti, B. 2021a. “Advanced Reactor Safeguards Program Overview.” Presented at the GAIN Advanced Reactors Safeguards and Security Workshop, April 2021. https://gain.inl.gov/SiteAssets/2021-April_SafeguardsAndSecurityWorkshop/Presentations/Safe_Secure_Day1_Website/01-ARS%20Overview-Cipiti.pdf.

Cipiti, B. 2021b. “Safeguards and Security Analysis for Fuel Cycle Facilities.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors, May 17, virtual meeting. https://www.nationalacademies.org/event/05-17-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-may-17-19-2021-meeting.

Cipiti, B. B., and N. Shoman. 2018. “Bulk Handling Facility Modeling and Simulation for Safeguards Analysis.” Science and Technology of Nuclear Installations 2018 (October 4):3967621. https://doi.org/10.1155/2018/3967621.

Cipiti, B. B., M. Browne, and M. Reim. 2021a. “The MPACT 2020 Milestone: Safeguards and Security by Design of Future Nuclear Fuel Cycle Facilities.” Journal of Nuclear Materials Management 49(1):5-21.

Cipiti, B. B., N. Shoman, and P. Honnold. 2021b. “Safeguards Modeling for Advanced Nuclear Facility Design.” Journal of Nuclear Materials Management 49(1):35-47.

Coates, C.W., B. L. Broadhead, A. M. Krichinsky, R. W. Leggett, M. B. Emmett, and J. B. Hines. 2005. “Radiation Effects on Personnel Performance Capability and a Summary of Dose Levels for Spent Research Reactor Fuels.” ORNL/TM-2005/261. Oak Ridge, TN: Oak Ridge National Laboratory, December 2005. https://technicalreports.ornl.gov/cppr/y2007/rpt/124368.pdf.

Coble, J. B., S. E. Skutnik, S. N. Gilliam, and M. P. Cooper. 2020. “Review of Candidate Techniques for Material Accountancy Measurements in Electrochemical Separations Facilities.” Nuclear Technology 206(12):1803-1826. December 1. https://doi.org/10.1080/00295450.2020.1724728.

Collins, E. D., G. D. Del Cul, B. B. Spencer, R. T. Jubin, C. Maher, I.-T. Kim, H. Lee, Y. S. Fedorov, V. F. Saprykin, V. I. Beznosyuk, A. B. Kolyadin, P. Baron, M. Miguirditchian, C. Sorel, Y. Morita, R. Taylor, A. Khaperskaya, C. Hill, R. Malmbeck, J. Law, G. de Angelis, L. Boucher, X. Xeres, E. Mendes, T. Inoue, J. P. Glatz, M. Kormilitsyn, J. Uhliř, V. Ignatiev, J. Serp, S. Delpech, K. Ikeda, S.-I. Koyama, M. Kurata, Y. Morita, K. Tsujimoto, and K. Minato. 2014. “Technology Readiness Assessment of Partitioning and Transmutation in Japan and Issues Toward Closed Fuel Cycle.” Progress in Nuclear Energy 74:242-263.

Crawford, D. C. 2020. “VTR Fuel Cycle and Waste Management.” Presented at the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors, online, December 7. https://www.nationalacademies.org/event/12-07-2020/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-december-7-8-2020-meeting.

Crawford, D. C., C. E. Baily, C. R. Clark, R. S. Fielding, and S. C. Marschman. 2019. “Fuel Fabrication Facility Study for FCF HALEU.” Idaho Falls, ID: Idaho National Laboratory, March 2019. https://gain.inl.gov/MicroreactorProgramTechnicalReports/Document-INL-EXT-19-52614_Rev.0.pdf.

Crimi, F P. 1995. “Shippingport Station Decommissioning Project ALARA Program.” In Proceedings of the Third International Workshop on the Implementation of ALARA at Nuclear Power Plants. Hauppauge, Long Island, NY: Brookhaven National Laboratory. https://www.osti.gov/biblio/54675.

Croce, M., D. Henzlova, H. Menlove, D. Becker, and J. Ullom. 2021. “Electrochemical Safeguards Measurement Technology Development at LANL.” Journal of Nuclear Materials Management 49(1):116-134.

Croff, A. G., and S. L. Krahn. 2016. “Comparative Assessment of Thorium Fuel Cycle Radiotoxicity.” Nuclear Technology 194(2):271-280. May 1. https://doi.org/10.13182/NT15-46.

Croff, A. G., R. G. Wymer, L. L. Tavlarides, J. H. Flack, and H. G. Larson. 2008. “Background, Status, and Issues Related to the Regulation of Advanced Spent Nuclear Fuel Recycle Facilities.” NUREG-1909. ACNW&M White Paper. Washington, DC: U.S. Nuclear Regulatory Commission, June 2008. https://www.nrc.gov/docs/ML0821/ML082100043.pdf.

Dalton, D. 2022. “Canda/Waste Organisation Unveils Plans for Spent Nuclear Fuel Transport.” Nucnet. January 7, 2022. https://www.nucnet.org/news/waste-organisation-unveils-plans-for-spent-nuclear-fuel-transport-1-5-2022.

Deep Isolation. 2002. “Technology.” Deep Isolation. https://www.deepisolation.com/technology. Accessed February 16, 2022.

Del Cul, G. D., B. B. Spencer, C. W. Forsberg, E. D. Collins, and W. S. Rickman. 2002. “TRISO-Coated Fuel Processing to Support High-Temperature Gas-Cooled Reactors.” Oak Ridge, TN: Oak Ridge National Laboratory, September 2002. https://info.ornl.gov/sites/publications/Files/Pub57144.pdf.

Delpech, S., E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le-Brun, X. Doligez, and G. Picard. 2009. “Reactor Physic and Reprocessing Scheme for Innovative Molten Salt Reactor System.” Fluorine and Nuclear Energy 130(1):11-17. January 1. https://doi.org/10.1016/j.jfluchem.2008.07.009.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Demkowicz, P. A. 2019. “TRISO Fuel: Design, Manufacturing, and Performance.” INL/MIS-19-52869-Revision-0. Idaho Falls, ID: Idaho National Laboratory, July 2019. https://inldigitallibrary.inl.gov/sites/sti/sti/Sort_24838.pdf.

Demkowicz, P. A., B. Liu, and J. D. Hunn. 2019. “Coated Particle Fuel: Historical Perspectives and Current Progress.” Journal of Nuclear Materials 515:434-450.

DeWitte, J. 2021. “Oklo.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, February 23, virtual meeting. https://www.nationalacademies.org/event/02-22-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-february-22-and-23-2021-meeting.

Dion, M. P., L. G. Worrall, S. Croft, and L. M. Scott. 2020. “Molten Salt Reactor Signatures and Modeling Study.” ORNL/SPR-2020/1836, November 2020. Oak Ridge National Laboratory.

Disser, J., E. Arthur, and J. Lambert, 2016. “Preliminary Safeguards Assessment for the Pebble-Bed Fluoride High-Temperature Reactor (PB-FHR) Concept.” INL/CON-16-38642. Idaho Falls, ID: Idaho National Laboratory. September 2016.

DNFSB (Defense Nuclear Facilities Safety Board). 2021. “Defense Nuclear Facilities Safety Board Staff Report: Savannah River Site H-Canyon Safety Basis Review.” https://www.dnfsb.gov/sites/default/files/document/24261/H-Canyon%20Exhaust%20Tunnel%20at%20the%20Savannah%20River%20Site%20%5B2021-100-030%5D.pdf.

DOE (U.S. Department of Energy). 1999. “Surplus Plutonium Disposition Final Environmental Impact Statement.” DOE/EIS-0283. Washington, DC: U.S. Department of Energy, November 1999. https://www.energy.gov/sites/prod/files/EIS-0283-FEIS_Vol3b-1999.pdf.

DOE. 2000. “Record of Decision for the Treatment and Management of Sodium-Bonded Spent Nuclear Fuel.” Federal Register 65(182). https://www.govinfo.gov/content/pkg/FR-2000-09-19/pdf/00-24005.pdf.

DOE. 2008. “U.S. Department of Energy Releases Revised Total System Life Cycle Cost Estimate and Fee Adequacy Report for Yucca Mountain Project.” Energy.gov, August 5, 2008. https://www.energy.gov/articles/us-department-energy-releases-revised-total-system-life-cycle-cost-estimate-and-fee.

DOE. 2009a. Federal Register, Notices, 74(123):31017-31018. June 29, 2009.

DOE. 2009b. Research Needs for Fusion-Fission Hybrid Systems. Report of the Research Needs Workshop (ReNeW). Gaithersburg, MD: U.S. Department of Energy, October 30, 2009. https://www.osti.gov/servlets/purl/972501-uKmLlN.

DOE. 2013. “Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste.” Washington, DC: U.S. Department of Energy, January 2013. https://www.energy.gov/sites/prod/files/Strategy%20for%20the%20Management%20and%20Disposal%20of%20Used%20Nuclear%20Fuel%20and%20High%20Level%20Radioactive%20Waste.pdf.

DOE. 2015a. “Advancing Clean Electric Power Technologies.” In Quadrennial Technology Review: An Assessment of Energy Technologies and Research Opportunities, 2015. https://www.energy.gov/sites/prod/files/2017/03/f34/quadrennial-technology-review-2015_1.pdf.

DOE. 2015b. Tritium and Enriched Uranium Management Plan Through 2060: Report to Congress. October 2015, http://fissilematerials.org/library/doe15b.pdf.

DOE. 2016. “Notice of Intent to Prepare a Supplemental Environmental Impact Statement for Disposition of Depleted Uranium Oxide Conversion Product Generated from DOE’s Inventory of Depleted Uranium Hexafluoride.” Federal Register 81(166):58921-58923.

DOE. 2017. “Alternatives for the Disposal of Greater-Than-Class C Low-Level Radioactive Waste and Greater-Than-Class C-Like Waste.” Report to the U.S. Congress. Washington, DC: U.S. Department of Energy, November 2017. https://www.energy.gov/sites/prod/files/2018/09/f55/GTCC-2017-Report-to-Congress-on-Disposal-Alternatives.pdf.

DOE. 2019. “DOE Standard: Nuclear Material Control and Accountability.” DOE-STD-1194-2019. Washington, DC: U.S. Department of Energy, September 2019. https://www.standards.doe.gov/standards-documents/1100/1194-astd-2019/@@images/file.

DOE. 2021. “Department of Energy: Nuclear Energy Advisory Committee.” Federal Register 86(240). December 17, 2021. https://www.govinfo.gov/content/pkg/FR-2021-12-17/pdf/FR-2021-12-17.pdf.

DOE. 2022a. “DOE Awards $36 Million to Reduce Waste from Advanced Nuclear Reactors.” Energy.gov, March 10, 2022. https://www.energy.gov/articles/doe-awards-36-million-reduce-waste-advanced-nuclear-reactors.

DOE. 2022b. “Energy Department Requests Proposals to Build and Test Second High-Tech Cask Railcar Design.” Energy. gov, January 24, 2022. https://www.energy.gov/ne/articles/energy-department-requests-proposals-build-and-test-second-high-tech-cask-railcar.

DOE. 2022c. “DOE/EIS-0542: Final Environmental Impact Statement.” Energy.Gov. May 13, 2022. https://www.energy.gov/nepa/articles/doeeis-0542-final-environmental-impact-statement.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

DOE. 2022d. “High Assay Low Enriched Uranium (HALEU) Cascade Demo Completion and Extended Production.” SAM. gov. 2022. https://sam.gov/opp/c9400feb96f04a988d142731f60ededc/view.

DOE. 2022e. “Spent Nuclear Fuel Management, Accelerated Basin De-Inventory Mission for H-Canyon, at the Savannah River Site” Federal Register 87(76): 23504–23506. https://www.govinfo.gov/content/pkg/FR-2022-04-20/pdf/2022-08383.pdf.

DOE. n.d.-a. “List of Licensed Transportation Packaging.” https://www.energy.gov/em/packaging-and-transportation.

DOE. n.d.-b. “WIPP Site.” U.S. Department of Energy’s Waste Isolation Pilot Plant. https://wipp.energy.gov/wipp-site.asp. Accessed August 12, 2021.

DOE-EM (Office of Environmental Management). 1997. “Linking Legacies: Connecting the Cold War Nuclear Weapons Production Processes to Their Environmental Consequences.” U.S. Department of Energy, January 1997. https://www.energy.gov/sites/default/files/2014/03/f8/Linking_Legacies.pdf.

DOE-EM. 2019. “Nuclear Regulatory Commission’s Low-Level Radioactive Waste Classifications.” https://www.energy.gov/sites/default/files/2019/06/f63/Nuclear-Regulatory-Commission%E2%80%99s-Low-Level-Radioactive-Waste-Classifications-June-2019.pdf.

DOE-EM. 2021. “Fact Sheet: Overview of the Moab UMTRA Project,” July 2021. https://www.gjem.energy.gov/documents/factsheets/OverviewFactSheet_July2021.pdf.

DOE-EM. n.d. “Packaging and Transportation.” Energy.gov. https://www.energy.gov/em/packaging-and-transportation.

DOE-NE (Office of Nuclear Energy). 2002. “The History of Nuclear Energy.” Washington, DC. https://www.energy.gov/sites/prod/files/The%20History%20of%20Nuclear%20Energy_0.pdf.

DOE-NE. 2007. “Global Nuclear Energy Partnership Strategic Plan.” GNEP-167312, Rev. 0. Washington, DC: U.S. Department of Energy, January 2007.

DOE-NE. 2019. “Advanced Reactor Technology Development Fact Sheet.” Energy.gov, January 16, 2019. https://www.energy.gov/ne/articles/advanced-reactor-technology-development-fact-sheet.

DOE-NE. 2020. “Infographic: Advanced Reactor Development” December 15, 2020. https://www.energy.gov/ne/articles/infographic-advanced-reactor-development.

DOE-NE. 2021a. “Office of Nuclear Energy: Strategic Vision.” January 8, 2021. https://www.energy.gov/sites/prod/files/2021/01/f82/DOE-NE%20Strategic%20Vision%20-Web%20-%2001.08.2021.pdf

DOE-NE. 2021b. “What Is a Nuclear Microreactor?” February 26, 2021, https://www.energy.gov/ne/articles/what-nuclear-microreactor.

DOE-NE. 2021c. “Advanced Small Modular Reactors (SMRs).” https://www.energy.gov/ne/advanced-small-modular-reactors-smrs. Accessed December 28, 2021.

DOE-NE. 2021d. “Next-Gen Nuclear Plant and Jobs are Coming to Wyoming.” November 16, 2021. https://www.energy.gov/ne/articles/next-gen-nuclear-plant-and-jobs-are-coming-wyoming.

DOE-NE. 2021e. “U.S. Department of Energy Seeks Input on Creation of HALEU Availability Program.” Energy.gov, December 14, 2021. https://www.energy.gov/ne/articles/us-department-energy-seeks-input-creation-haleu-availability-program.

DOE-NE. 2021f. “Centrus Becomes First U.S. Licensed HALEU Production Facility.” Energy.gov, June 23, 2021. https://www.energy.gov/ne/articles/centrus-becomes-first-us-licensed-haleu-production-facility.

DOE-NE. 2021g. “Request for Information (RFI) Regarding Planning for Establishment of a Program to Support the Availability of High-Assay Low-Enriched Uranium (HALEU) for Civilian Domestic Research, Development, Demonstration, and Commercial Use.” Federal Register 86(237). December 14, 2021. https://www.govinfo.gov/content/pkg/FR-2021-12-14/pdf/2021-26984.pdf.

DOE-NE. 2021h. Federal Register. 2021. “Notice of Request for Information (RFI) on Using a Consent-Based Siting Process to Identify Federal Interim Storage Facilities,” December 1, 2021. https://www.federalregister.gov/documents/2021/12/01/2021-25724/notice-of-request-for-information-rfi-on-using-a-consent-based-siting-process-to-identify-federal.

DOE-NE. 2022a. “U.S. Department of Energy Selects New Members to Nuclear Advisory Team, Revises Function and Focus.” Energy.gov, February 9, 2022. https://www.energy.gov/ne/articles/us-department-energy-selects-new-members-nuclear-advisory-team-revises-function-and.

DOE-NE. 2022b. “Final Versatile Test Reactor Environmental Impact Statement: Volume 2, Appendices A-H.” DOE/EIS-0542. Idaho Falls, ID: U.S. Department of Energy. https://www.energy.gov/sites/default/files/2022-05/final-eis-0542-versatile-test-reactor-vol-2-2022-05.pdf.

DOE-NE. n.d.-a. “Bilateral Cooperation.” Energy.gov. https://www.energy.gov/ne/nuclear-reactor-technologies/international-nuclear-energy-policy-and-cooperation/bilateral. Accessed February 23, 2022.

DOE-NE. n.d.-b. “Nuclear Energy Advisory Committee.” https://www.energy.gov/ne/nuclear-energy-advisory-committee. Accessed January 1, 2022.

DOE-NNSA (National Nuclear Security Administration). n.d.-a. “Office of Secure Transportation.” Energy.gov. https://www.energy.gov/nnsa/office-secure-transportation.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

DOE-NNSA. n.d.-b. “National Nuclear Security Administration.” Energy.gov. https://www.energy.gov/nnsa/national-nuclear-security-administration.

DOE-RW (Office of Civilian Radioactive Waste Management). 2008. “Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites.” DOE/RW-0596. Washington, DC: U.S. Department of Energy, December 2008. https://www.nrc.gov/docs/ML0834/ML083450160.pdf.

DOS (U.S. Department of State). 2010. Treaty on the Non-Proliferation of Nuclear Weapons. October 6. https://www.state.gov/wp-content/uploads/2019/03/228-Nuclear-Nonproliferation-Treaty-508.pdf. Accessed April 21, 2022.

DOS. n.d. “Nuclear Non-Proliferation Treaty.” U.S. Department of State. https://www.state.gov/nuclear-nonproliferation-treaty.

Drain, F., J. L. Emin, R. Vinoche, and P. Baron. 2008. “COEX - Process: Cross-Breeding Between Innovation and Industrial Experience.” Proceedings of Waste Management Symposium 2008. Tempe, AZ, United States. https://www.osti.gov/biblio/21319762.

Dungan, K., G. Butler, F. R. Livens, and L. M. Warren. 2017. “Uranium from Seawater—Infinite Resource or Improbable Aspiration?” Progress in Nuclear Energy 99(August 1):81-85. https://doi.org/10.1016/j.pnucene.2017.04.016.

Durst, P. C., I. Therios, R. Bean, A. Dougan, B. Boyer, R. Wallace, M. H Ehinger, D. N. Kovacic, and K. Tolk. 2007. “Advanced Safeguards Approaches for New Reprocessing Facilities.” PNNL-16674. Richland, WA: Pacific Northwest National Laboratory, June 24, 2007. https://doi.org/10.2172/949149.

Durst, P. C., D. Beddingfield, B. Boyer, R. Bean, M. Collins, M. Ehinger, D. Hanks, D. L Moses, and L. Refalo. 2009. “Nuclear Safeguards Considerations for the Pebble Bed Modular Reactor (PBMR).” INL/EXT-09-16782. Idaho Falls, ID: Idaho National Laboratory, October 1, 2009. https://doi.org/10.2172/968683.

Ebbinghaus, B. B., C. G. Bathke, D. S. Dalton, and J. P. Murphy. 2013. “The Application of Material Attractiveness in a Graded Approach to Nuclear Materials Security.” LLNL-CONF-640708. Salt Lake City, UT. https://www.osti.gov/biblio/1097225.

EIA (U.S. Energy Information Administration). 2020. “2019 Domestic Uranium Production Report,” May 2020. https://www.eia.gov/uranium/production/annual/pdf/uprodshiptbl3.pdf.

EIA. 2021a. “Nuclear Explained: Where Our Uranium Comes From.” U.S. Energy Information Administration, July 2, 2021. https://www.eia.gov/energyexplained/nuclear/where-our-uranium-comes-from.php.

EIA. 2021b. “Annual Energy Outlook 2021 with Projections to 2050.” AEO 2021 Narrative. Washington, DC: U.S. Energy Information Administration, February 2021. https://www.eia.gov/outlooks/aeo/pdf/AEO_Narrative_2021.pdf.

EIA. 2021c. “Nuclear Explained: U.S. Nuclear Industry.” U.S. Energy Information Administration, April 6, 2021. www.eia.gov/energyexplained/nuclear/us-nuclear-industry.php.

EIA. 2022. “Table 8.1 Nuclear Energy Overview,” February 2022. https://www.eia.gov/totalenergy/data/monthly/pdf/sec8_3.pdf.

Energy Fuels. 2018. “Ur-Energy and Energy Fuels Announce U.S. Department of Commerce Has Initiated Investigation into Effects of Uranium Imports on U.S. National Security.” Energy Fuels, July 18, 2018. https://www.energyfuels.com/2018-07-18-Ur-Energy-and-Energy-Fuels-Announce-U-S-Department-of-Commerce-Has-Initiated-Investigation-into-Effects-of-Uranium-Imports-on-U-S-National-Security.

ENS (Environment News Service). 2022. “UK Local Governments Demand Plutonium Safety Upgrades.” ENS Newswire, February 12, 2022. https://ens-newswire.com/uk-local-governments-demand-plutonium-safety-upgrades.

EPRI (Electric Power Research Institute). 1991. “An Evaluation of the Concept of Transuranic Burning Using Liquid Metal Reactors.” Electric Power Research Institute. http://inis.iaea.org/search/search.aspx?orig_q=RN:22056446.

EPRI. 2007. “An Economic Analysis of Select Fuel Cycles Using the Steady-State Analysis Model for Advanced Fuel Cycles Schemes (SMAFS).” Technical Update 1015387. Palo Alto, CA: Electric Power Research Institute.

EPRI. 2009a. “Program on Technology Innovation: Readiness of Existing and New U.S. Reactors for Mixed-Oxide (MOX) Fuel.” Technical Update. Palo Alto, CA: Electric Power Research Institute, May 2009. https://www.epri.com/research/products/1018896.

EPRI. 2009b. Electric Power Research Institute. 2009. “Nuclear Fuel Cycle Cost Comparison Between Once-Through and Plutonium Single-Recycling in Pressurized Water Reactors.” 1018575. Palo Alto, CA: Electric Power Research Institute. https://www.epri.com/research/products/1018575.

EPRI. 2010a. “Parametric Study of Front-End Nuclear Fuel Cycle Costs Using Reprocessed Uranium.” No. 1020659. Technical Report. Palo Alto, CA: Electric Power Research Institute, January 2010.

EPRI. 2010b. “Advanced Nuclear Fuel Cycles—Main Challenges and Strategic Choices, Report No. 1020307, A. Machiels and A. Sowder. Palo Alto, CA: Electric Power Research Institute, September 2010. https://www.epri.com/research/products/1020307.

EPRI. 2010c. “Nuclear Fuel Cycle Cost Comparison Between Once-Through and Plutonium Multi-Recycling in Fast Reactors.” 1020660. Palo Alto, CA: Electric Power Research Institute. https://www.epri.com/research/products/1020660.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

EPRI. 2010d. “Nuclear Fuel Cycle Cost Comparison Between Once-Through and Fully Closed Cycles.” 1021054. Palo Alto, CA: Electric Power Research Institute.

EPRI. 2019. “Uranium Oxycarbide (UCO) Tristructural Isotropic (TRISO) Coated Particle Fuel Performance.” Technical Report EPRI-AR-1(NP). Palo Alto, CA: Electric Power Research Institute, May 2019. https://www.nrc.gov/docs/ML1915/ML19155A173.pdf.

EPRI. 2020. “Feasibility of Borehole Co-Location with Advanced Reactors for Onsite Management of Spent Nuclear Fuel.” Technical Report 3002019751. Palo Alto, CA: Electric Power Research Institute. https://www.epri.com/research/products/000000003002019751.

EPRI. 2021a. “Evaluation of Chloride Fuel Salt Lifetime in a Fast-Spectrum, Liquid-Fuel Molten Salt Reactor.” 3002021038. Technical Report. Palo Alto, CA: Electric Power Research Institute. https://www.epri.com/research/products/000000003002021038.

EPRI. 2021b. “Extended Storage Collaboration Program (ESCP) Winter 2021.” EPRI. 2021. https://www.epri.com/events/8B781C3A-CD5F-48DC-96BA-9B570F6FD432.

EPRI. 2022. “Program 41.03.01: Used Fuel and High-Level Waste Management Program—Overview.” EPRI. 2022. https://www.epri.com/research/programs/061149/overview.

Evans-Worrall, L. 2021. “Safeguards Technology Considerations and Research Needs for Thorium Fuel Cycles and Molten Salt Reactors.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, October 15, virtual meeting. https://www.nationalacademies.org/event/10-14-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-11-public-sessions-october-14-15-2021.

Ewing, R.C. 1995. “Radioactive Waste Forms: A Review and Comparison.” In Radioactive Waste Management Practices and Issues in Developing Countries: Proceedings of a Seminar Held in Beijing, China, 10-14 October 1994. IAEA-TECDOC-851. Vienna, Austria: International Atomic Energy Agency. https://inis.iaea.org/collection/NCLCollectionStore/_Public/27/042/27042093.pdf.

Ewing, R. C. 2011. “Standards and Regulations for the Geologic Disposal of Spent Nuclear Fuel and High-Level Waste.” Prepared for the Blue Ribbon Commission on America’s Nuclear Future. Ann Arbor, MI: University of Michigan. https://fsi-live.s3.us-west-1.amazonaws.com/s3fs-public/ewing_brc_white_paper_final.pdf.

Ewing, R. C. 2015. “Long-Term Storage of Spent Nuclear Fuel.” Nature Materials 14(March 2015):252-257. https://doi.org/10.1038/nmat4226.

Ewing, R. C., and L. M. Wang. 2002. “Phosphates as Nuclear Waste Forms.” Reviews in Mineralogy and Geochemistry 48(1):673-699. https://doi.org/10.2138/rmg.2002.48.18.

Ewing, R. C., and S. Park. 2021. “The Concept of Geological Disposal of Highly Radioactive Nuclear Waste.” Encyclopedia of Nuclear Energy. https://doi.org/10.1016/B978-0-12-819725-7.00156-2.

Fachinger, J., M. den Exter, B. Grambow, S. Holgersson, C. Landesman, M. Titov, and T. Podruhzina. 2006. “Behaviour of Spent HTR Fuel Elements in Aquatic Phases of Repository Host Rock Formations.” HTR-2004 236(5) (March 1):543-554. https://doi.org/10.1016/j.nucengdes.2005.11.023.

Ferroni, P., F. Franceschini, and A. Levinsky. 2021. Updated information from “Westinghouse Lead Fast Reactor.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, October 15, virtual meeting. https://www.nationalacademies.org/event/10-14-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-11-public-sessions-october-14-15-2021.

Fisher, M. J., M. H. Holmes, and S. W. Chestnutt. 1996. “Fort St. Vrain Decommissioning Experience.” Transactions of the American Nuclear Society 75(December 31, 1996). https://www.osti.gov/biblio/426590.

Flanagan, G., T. Fanning, and T. Sofu. 2015. “Sodium-Cooled Fast Reactor (SFR) Technology and Safety Overview.” Presented at the Sodium-Cooled Fast Reactor Technology Seminar, Washington, DC, February 18, 2015. https://gain.inl.gov/SiteAssets/Fast%20Reactors/SFR-NRCTechnologyandSafetyOverview18Feb15.pdf.

Fletcher, D. 2020. “URENCO Next Generation Fuels: Conversion and Enrichment Options.” Presented at the HALEU Webinar, April 28. https://gain.inl.gov/HALEU_Webinar_Presentations/11-Fletcher,URENCO-28Apr2020.pdf.

Flibe Energy. 2022. “LFTR Technology.” Flibe Energy, 2022. https://flibe-energy.com/lftr.

Forsberg, C. W. 2007. “Thermal- and Fast-Spectrum Molten Salt Reactors for Actinide Burning and Fuel Production.” In Proceedings of GLOBAL 2007 Conference on Advanced Nuclear Fuel Cycles and Systems. Boise, ID: American Nuclear Society, September 9-13, 2007.

Forsberg, C. W., and E. Greenspan. 2003. “Molten Salt Reactors (MSRs): Coupling Spent Fuel Processing and Actinide Burning.” In Advances in Nuclear Fuel Management III (ANFM 2003). Hilton Head, SC: American Nuclear Society. https://technicalreports.ornl.gov/cppr/y2001/pres/118013.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Forsberg, C. and P. F. Peterson. 2015. Spent Nuclear Fuel and Graphite Management for Salt-Cooled Reactors: Storage, Safeguards, and Repository Disposal. Nuclear Technology 191(2):113-121. https://doi.org/10.13182/NT14-88.

Forsberg, C. W., C. M. Hopper, J. L. Richter, and H. C. Vantine. 1998. “Definition of Weapons-Usable Uranium-233.” ORNL/TM-13517. Oak Ridge, TN: Oak Ridge National Laboratory. http://inis.iaea.org/search/search.aspx?orig_q=RN:29058723.

Forsberg, C. W., S. Lam, D. M. Carpenter, D. G. Whyte, R. Scarlat, C. Contescu, L. Wei, J. Stempien, and E. Blandford. 2017. “Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward.” Nuclear Technology 197(2):119-139. https://doi.org/10.13182/NT16-101.

Fort, J. A., D. J. Richmond, B. J. Jensen, and S. R. Suffield. 2019. “High-Burnup Demonstration: Thermal Modeling of TN-32B Vacuum Drying and ISFSI Transients.” Richland, WA: Pacific Northwest National Laboratory, September 20, 2019. https://doi.org/10.2172/1568885.

Frank, S. M., and M. N. Patterson. 2014. “Electrorefiner Salt Disposition Technical Evaluation.” TEV-2201. Idaho National Laboratory.

Frank, S., W. Ebert, B. Riley, H. Seo Park, C. H. Lee, M. K. Jeon, J. H. Yang, and H. C. Eun. 2015. “Waste Stream Treatment and Waste Form Fabrication for Pyroprocessing of Used Nuclear Fuel.” INL/EXT-14-34014. Idaho Falls, ID: Idaho National Laboratory, July 2015. https://inldigitallibrary.inl.gov/sites/sti/sti/6597429.pdf.

Fredrickson, G. L., G. Cao, R. Gakhar, and T.-S. Yoo. 2018. “Molten Salt Reactor Salt Processing—Technology Status.” INL/EXT-18-51033-Rev000. Idaho Falls, Idaho: Idaho National Laboratory, August 29, 2018. https://doi.org/10.2172/1484689.

Freeze, G., E. Bonano, P. Swift, E. Kalinina, E. Hardin, L. Price, S. Durbin, R. Rechard, and K. Gupta. 2021. “Integration of the Back End of the Nuclear Fuel Cycle.” SAND2021-10444. Albuquerque, NM: Sandia National Laboratory, August 1, 2021. https://doi.org/10.2172/1817319.

Frieß, F., M. Kütt, and M. Englert. 2015. “Proliferation Issues Related to Fast SMRs.” Annals of Nuclear Energy (Oxford) 2015:725-731.

FRWG (Fast Reactor Working Group). 2018. “Nuclear Metal Fuel: Characteristics, Design, Manufacturing, Testing, and Operating History,” June 2018. https://www.nrc.gov/docs/ML1816/ML18165A249.pdf.

Fuks, L., I. Herdzik-Koniecko, K. Kiegiel, and G. Zakrzewska-Koltuniewicz. 2020. “Management of Radioactive Waste Containing Graphite: Overview of Methods.” Energies 13(18). https://doi.org/10.3390/en13184638.

Fukuda, K., T. Ogawa, S. Kashimura, K. Ikawa, K. Iwamoto, K. Yamamoto, T. Itoh, and H. Matsushima. 1982. “Release Behavior of Fission Gas from Coated Fuel Particles under Irradiation.” Journal of Nuclear Science and Technology 19(11):889-902. https://doi.org/10.1080/18811248.1982.9734235.

GA (General Atomics). 2019. “Status Report—EM2.” Advanced Reactors Information System. International Atomic Energy Agency. September 30, 2019. https://aris.iaea.org/PDF/EM2(GeneralAtomics)_2020.pdf.

GAO (U.S. Government Accountability Office). 1977. “Issues Related to the Closing of the Nuclear Fuel Services, Incorporated, Reprocessing Plant at West Valley, New York.” Washington, DC. https://www.gao.gov/assets/emd-77-27.pdf.

GAO. 2011. Commercial Nuclear Waste: Effects of a Termination of the Yucca Mountain Repository Program and Lessons Learned. (GAO-11-229). Washington, DC: U.S. Government Accountability Office. https://www.gao.gov/assets/gao-11-229.pdf. Accessed March 15, 2022.

GAO. 2013a. “Managing Critical Isotopes: Stewardship of Lithium-7 Is Needed to Ensure a Stable Supply.” GAO-13-716. Washington, DC: U.S. Government Accountability Office. https://www.gao.gov/assets/gao-13-716.pdf.

GAO. 2013b. “Department of Energy: Concerns with Major Construction Projects at the Office of Environmental Management and NNSA.” GAO-13-484T. Washington, DC: U.S. Government Accountability Office, March 20, 2013. https://www.gao.gov/assets/gao-13-484t.pdf.

GAO. 2017. Benefits and Costs Should Be Better Understood Before DOE Commits to a Separate Repository for Defense Waste. Report to congressional addressees. GAO-17-174. https://www.gao.gov/assets/gao-17-174.pdf.

GAO. 2018. “NNSA Should Clarify Long-Term Uranium Enrichment Mission Needs and Improve Technology Cost Estimates,” GAO-18-126, Washington, DC: U.S. Government Accountability Office, February 2018, https://www.gao.gov/assets/gao-18-126.pdf.

GAO. 2019. “Surplus Plutonium Disposition: NNSA’s Long-Term Plutonium Oxide Production Plans Are Uncertain.” GAO-20-166. Washington, DC: U.S. Government Accountability Office, October 2019. https://www.gao.gov/assets/gao-20-166.pdf.

GAO. 2020. “Hanford Waste Treatment Plant: DOE Is Pursuing Pretreatment Alternatives, But Its Strategy Is Unclear While Costs Continue to Rise” (Accessible Version) (GAO-20-363). Washington, DC: U.S. Government Accountability Office. https://www.gao.gov/assets/710/707110.pdf. Accessed March 15, 2022.

GAO. 2021a. “Commercial Spent Nuclear Fuel: Congressional Action Needed to Break Impasse and Develop a Permanent Solution.” Washington, DC: U.S. Government Accountability Office, September 2021. https://www.gao.gov/assets/gao-21-603.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

GAO. 2021b. “Nuclear Waste Disposal: Actions Needed to Enable DOE Decision That Could Save Tens of Billions of Dollars.” GAO-22-104365. Washington, DC: U.S. Government Accountability Office, December 2021. https://www.gao.gov/assets/gao-22-104365.pdf.

Garrett, A. G., S. L. Garrett, R. J. Marek, M. R. Mitchell, C. R. Orton, R. T. Otto, T. Sobolev, and D. C. Springfels. 2021. “Advanced Reactor Safeguards: Lessons from the IAEA Safeguards Domain.” PNNL-31977. Richland, WA: Pacific Northwest National Laboratory, September 2021. https://gain.inl.gov/SiteAssets/AdvancedReactorSafeguards/KeyThrustArea5/PNNL-31977_ARS_IAEA_Interfaces.pdf.

Gay, A. 2021. “Back-End of the Nuclear Fuel Cycle: Existing Recycling Solution at Orano.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 15, virtual meeting. https://www.nationalacademies.org/event/09-13-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-9-september-13-15-2021.

Gerczak, T. J., R. L. Seibert, J. D. Hunn, C. A. Baldwin, F. C. Montgomery, and R. N. Morris. 2020. “Redistribution of Radionuclides in Irradiated AGR-1 UCO TRISO Fuel after 1800°C Safety Testing.” Journal of Nuclear Materials 542(December 15):152453. https://doi.org/10.1016/j.jnucmat.2020.152453.

GIF (Generation IV International Forum). 2021a. “Sodium-Cooled Fast Reactor (SFR).” Generation IV Systems, 2021. https://www.gen-4.org/gif/jcms/c_9361/sfr.

GIF. 2021b. “Gas-Cooled Fast Reactor (GFR).” Generation IV Systems, 2021. https://www.gen-4.org/gif/jcms/c_42148/gas-cooled-fast-reactor-gfr.

GIF. 2021c. “Lead-Cooled Fast Reactor (LFR).” Generation IV Systems, 2021. https://www.gen-4.org/gif/jcms/c_42149/lead-cooled-fast-reactor-lfr.

GIF. 2021d. “Molten Salt Reactor.” Generation IV Systems, 2021. https://www.gen-4.org/gif/jcms/c_9359/msr.

GIF. 2022a. “Very-High-Temperature Reactor.” Generation IV International Forum. https://www.gen-4.org/gif/jcms/c_42153/very-high-temperature-reactor-vhtr.

GIF. 2022b. Annual Report 2021. https://www.gen-4.org/gif/jcms/c_203440/gif-2021-ar.

GIF and NERAC (U.S. Nuclear Energy Research Advisory Committee). 2002. “A Technology Roadmap for Generation IV Nuclear Energy Systems: Ten Nations Preparing Today for Tomorrow’s Energy Needs.” GIF-002-00. https://www.gen-4.org/gif/upload/docs/application/pdf/2013-09/genivroadmap2002.pdf.

GIF Experts’ Group. 2010. “Use of Thorium in the Nuclear Fuel Cycle: How Should Thorium Be Considered in the GIF?” Generation IV International Forum, December 23, 2010. https://www.gen-4.org/gif/upload/docs/application/pdf/2013-10/gif_egthoriumpaperfinal.pdf.

Giraud, A. L. 1983. “Energy in France.” Annual Review of Energy and the Environment 8:165-191. https://www.annualreviews.org/doi/pdf/10.1146/annurev.eg.08.110183.001121.

Gitau, E. T., and W. S. Charlton. 2012. “Use of a Microsphere Fingerprint for Identity Verification of Fuel Pebbles in a Pebble-Fueled HTGR.” Journal of Nuclear Materials Management 40(2):19-24.

Glaser, A. 2006. “On the Proliferation Potential of Uranium Fuel for Research Reactors at Various Enrichment Levels.” Science and Global Security 14(1):1-24. https://doi.org/10.1080/08929880600620542.

Goldner, A. and S. McKee. 2021. “Perspectives from Congress: Panel Discussion with Key Staff of the Appropriations Committees of the Senate and House of Representatives.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, December 6, virtual meeting. https://www.nationalacademies.org/event/12-06-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-12-december-6-7-2021.

Gougar, H. D. 2018. “Gas-Cooled Fast Reactor Research and Development Roadmap.” United States: Idaho National Laboratory. May 3. https://doi.org/10.2172/1599068.

Grambow, B. 2008. “Mobile Fission and Activation Products in Nuclear Waste Disposal.” Radiogeochemical Aspects of Nuclear Waste Disposal 102(3):180-186. https://doi.org/10.1016/j.jconhyd.2008.10.006.

Grambow, B. 2021. “Some Impacts of Advanced Fuel Cycle Options on Waste Management and Long Term Disposal Safety.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, June 7, virtual meeting. https://www.nationalacademies.org/event/06-07-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-6-part-2-june-7-2021.

Grambow, B., A. Loida, A. Martinez-Esparza, P. Diaz-Arocas, J. de Pablo, J-L. Paul, G. Marx, J.-P. Glatz, K. Lemmens, K. Ollila, and H. Christensen. 2000. “Source Term for Performance Assessment of Spent Fuel as a Waste Form.” EUR19140 Report. Nuclear Science and Technology. European Commission. https://www.nrc.gov/docs/ML0334/ML033460436.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Grambow, B., A. Abdelouas, D. Greneche, M.H. Mouliney, J. Fachinger, A. Bukaemsky, S. Neumann, and M. Titov. 2006. “Study of Various Options for Final Disposal of HTR Coated Particles.” In Proceedings HTR2006. Johannesburg, South Africa, 2006.

Grambow, B., A. Abdelouas, F. Guittonneau, J. Vandenborre, J. Fachinger, W. von Lensa, P. Bros, D. Roudil, J. Perko, J. Marivoet, A. Sneyers, D. Millington, and F. Cellier. 2008. “The Backend of the Fuel Cycle of HTR/VHTR Reactors.” In Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology 2:649-657. Washington, DC. https://doi.org/10.1115/HTR2008-58177.

Grambow, B., A. Abdelouas, F. Guittonneau, J. Vandenborre, W. von Lensa, P. Bros, and D. Roudil. 2010. “The Option of Geological Disposal of Spent (V)HTR Fuel.” In Proceedings of HTR 2010, Paper 266. Prague, Czech Republic.

Grebennikova, T., A. N. Jones, and C. A. Sharrad. 2021. “Electrochemical Decontamination of Irradiated Nuclear Graphite from Corrosion and Fission Products Using Molten Salt.” Energy and Environmental Science 14(10):5501-5512. https://doi.org/10.1039/D1EE00332A.

Grenthe, I., J. Fuger, R. J. Konings, R. J. Lemire, A. B. Muller, C. Nguyen-Trung, and H. Wanner. 1992. Chemical thermodynamics of uranium (vol. 1) Amsterdam: Elsevier.

Griffith, A. 2020. “Overview of DOE-NE’s Fuel Cycles Work.” Presentation to the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 21, virtual meeting. https://www.nationalacademies.org/event/09-21-2020/merits-and-viability-of-different-nuclear-fuel-cycles-andtechnology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-september-21-23-2020-meeting.

Griffith, A. 2021. “Office of Nuclear Energy HALEU Availability Program FY2022 Proposed Activities.” Presentation to the Committee on the Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors, September 28, virtual meeting. https://www.nationalacademies.org/event/09-28-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-10-september-28-29-2021-public-sessions.

Guidez, J. 2013. Phénix. Le Retour d’expérience. EDP Sciences.

Guidez, J. 2017. “Phenix and Superphenix Feedback Experience.” Presented at the Gen IV International Forum Webinar, 2017. https://www.gen-4.org/gif/upload/docs/application/pdf/2017-12/gifiv_webinar_phenix_superphenix_final_guidez.pdf.

Guittonneau, F., A. Abdelouas, and B. Grambow. 2010. “HTR Fuel Waste Management: TRISO Separation and Acid-Graphite Intercalation Compounds Preparation.” Journal of Nuclear Materials 407(2):71-77. https://doi.org/10.1016/j.jnucmat.2010.09.026.

Haghighi, M., M. Ford, R. Szozda, and M. Jugan. 2002. “Waste Stream Generated and Waste Disposal Plans for Molten Salt Reactor Experiment at Oak Ridge National Laboratory.” WM’02 Conference, February 24-28, 2002. Tucson, AZ. https://digital.library.unt.edu/ark:/67531/metadc782704/m1/1.

Hall, N., X. He, and Y.-M. Pan. 2019a. “Disposal Options and Potential Challenges to Waste Packages and Waste Forms in Disposal of Spent (Irradiated) Advanced Reactor Fuel Types.” San Antonio, TX: Center for Nuclear Waste Regulatory Analyses, December 2019. https://www.nrc.gov/docs/ML2023/ML20237F397.pdf.

Hall, N., X. He, Y.-M. Pan, and P. LaPlante. 2019b. “Potential Challenges with Storage of Spent (Irradiated) Advanced Reactor Fuel Types.” San Antonio, TX: Center for Nuclear Waste Regulatory Analysis, August 2019. https://www.nrc.gov/docs/ML2002/ML20022A217.pdf.

Hall, N., X. He, Y.-M. Pan, and P. LaPlante. 2020. “Transportation Experience and Potential Challenges with Transportation of Spent (Irradiated) Advanced Reactor Fuel Types.” Prepared for U.S. Nuclear Regulatory Commission. San Antonio, TX: Center for Nuclear Waste Regulatory Analysis, January 2020.

Hanks, D. H. 2021. “Implementation of IAEA Safeguards Within the United States.” Presentation to the Presentation to the National Academies of Sciences, Engineering, and Medicine’s Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 14, 2021. https://www.nationalacademies.org/event/09-13-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-9-september-13-15-2021.

Harp, J. M., S. L. Hayes, P. G. Medvedev, D. L. Porter, and L. Capriotti. 2017. “Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report.” Idaho National Laboratory. NTRD-FUEL-2017-00148. September 2017. https://www.osti.gov/servlets/purl/1458766.

Hawari, A. I., and J. Chen. 2005. “Computational Investigation of On-Line Interrogation of Pebble Bed Reactor Fuel.” IEEE Transactions on Nuclear Science 52(5):1659-1664. October. https://doi.org/10.1109/TNS.2005.856760.

Hedin, A. 1997. “Spent Nuclear Fuel—How Dangerous Is It?” Stockholm, Sweden: Swedish Nuclear Fuel and Waste Management Co., March.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Hejzlar, P. 2021. “Terrapower: Fuel Cycle and Waste Management.” Presentation to the National Academies of Sciences, Engineering, and Medicine’s Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, February 22.

Higgins, M., N. Shoman, and B. Cipiti. 2021 “Limitations of Overall Measurement Error for Molten Salt Reactors.” In Proceedings of the INMM and ESARDA Joint Virtual Annual Meeting, August 23-26 and August 30-September 1. https://resources.inmm.org/sites/default/files/2021-09/a190.pdf.

Hill, R. 2021. “Sodium-Cooled Fast Reactor Technologies.” Presentation to the National Academies of Sciences, Engineering, and Medicine’s Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, October 14, 2021. https://www.nationalacademies.org/event/10-14-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-11-public-sessions-october-14-15-2021.

Hogue, K. K., P. Gibbs, M. P. Dion, and M. Poore. “Domestic Safeguards Material Control and Accountancy Considerations for Molten Salt Reactors.” ORNL/SPR/150504. Oak Ridge, TN: Oak Ridge National Laboratory, February 2021. https://gain.inl.gov/SiteAssets/2021-April_SafeguardsAndSecurityWorkshop/Reading/Domestic%20Safeguards%20Material%20Control%20and%20Accountancy%20Considerations%20for%20Molten%20Salt%20Reactors%20-%20ORNL.pdf.

Holcomb, D. 2017. “Module 2: Overview of MSR Technology and Concepts.” Presentation for U.S. Nuclear Regulatory Commission Staff, Washington, DC, November 7-8, 2017. https://www.nrc.gov/docs/ML1733/ML17331B114.pdf.

Holcomb, D. E. 2015. “Molten Salt Reactors Today: Status and Challenges.” Presented at the Workshop on MSR Technologies—Commemorating the 50th Anniversary of the Startup of the MSRE, Oak Ridge National Laboratory, October 15, 2015. https://msrworkshop.ornl.gov/msr2015.

Holcomb, D. E., G. F. Flanagan, B. W. Patton, J. C. Gehin, R. L. Howard, and T. J. Harrison. 2011. “Fast Spectrum Molten Salt Reactor Options.” ORNL/TM-2011/105. Oak Ridge, TN: Oak Ridge National Laboratory, July 2011. https://info.ornl.gov/sites/publications/Files/Pub29596.pdf.

Hollenbach, D. F., and C. M. Hopper. 1997. “Criticality Safety Considerations for MSRE Fuel Drain Tank Uranium Aggregation.” CONF-970926-4. Topical Meeting on Criticality Safety Challenges in the Next Decade, Chelan, Washington, September 7-11, 1997. https://www.osti.gov/biblio/515562.

Holt, M. 2021a. “Civilian Nuclear Waste Disposal.” Washington, DC: Congressional Research Service, September 17, 2021. https://sgp.fas.org/crs/misc/RL33461.pdf.

Holt, M. 2021b. “Nuclear Energy: Overview of Congressional Issues.” Washington, DC: Congressional Research Service, October 20. https://crsreports.congress.gov/product/pdf/R/R42853.

Holt, M., and M. B. D. Nikitin. 2017. “Mixed-Oxide Fuel Fabrication Plant and Plutonium Disposition: Management and Policy Issues.” Washington, DC: Congressional Research Service, December 14, 2017. https://fas.org/sgp/crs/nuke/R43125.pdf.

Holzman, J., and H. Northey. 2022. “Could Russia’s Invasion of Ukraine Revive U.S. Uranium Mining?” E&E News: Greenwire. March 18, 2022. https://www.eenews.net/articles/could-russias-invasion-of-ukraine-revive-u-s-uranium-mining.

Hombourger, B., J. Křepel, and A. Pautz. 2019. “Breed-and-Burn Fuel Cycle in Molten Salt Reactors.” EPJ Nuclear Sciences & Technologies 5. https://doi.org/10.1051/epjn/2019026.

Hoyt, N. C., C. A. Launiere, and E. A. Stricker. 2021. “In-Process Monitoring of Molten Salt Composition by Voltammetry and Automated Sampling-Based Techniques.” Journal of Nuclear Materials Management 49(1):87-98.

Huff, K. D. 2019. “Chapter One—Economics of Advanced Reactors and Fuel Cycles.” In Storage and Hybridization of Nuclear Energy, edited by H. Bindra and S. Revankar, pp. 1-20. Academic Press. https://doi.org/10.1016/B978-0-12-813975-2.00001-6.

Huff, K. D. 2021. “Perspectives from the Department of Energy’s Office of Nuclear Energy.” Presented at the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, December 6.

Humrickhouse, P. W. 2011. “HTGR Dust Safety Issues and Needs for Research and Development.” INL/EXT-11-21097. Idaho Falls, ID: Idaho National Laboratory. June. https://inldigitallibrary.inl.gov/sites/sti/sti/5026004.pdf.

Hyatt, N. C. 2020. “Safe Management of the UK Separated Plutonium Inventory: A Challenge of Materials Degradation.” NPJ Materials Degradation 4:28. https://doi.org/10.1038/s41529-020-00132-7.

IAEA (International Atomic Energy Agency). 1970. “Treaty on the Non-Proliferation of Nuclear Weapons,” INFCIRC/140. April 22, 1970. https://www.iaea.org/sites/default/files/publications/documents/infcircs/1970/infcirc140.pdf.

IAEA. 1975. “The Physical Protection of Nuclear Material,” INFCIRC/225. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/sites/default/files/publications/documents/infcircs/1975/infcirc225.pdf.

IAEA. 1980. “The Convention on the Physical Protection of Nuclear Material.” INFCIRC/274/Rev. 1. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/sites/default/files/infcirc274r1.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

IAEA. 1981. “The Text of the Agreement of 18 November 1977 Between the United States of America and the Agency for the Application of Safeguards in the United States of America.” INFCIRC/288. Information Circular. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/sites/default/files/infcirc288.pdf.

IAEA. 1982. Nuclear Power, the Environment and Man. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/3478/nuclear-power-the-environment-and-man.

IAEA. 1985. IAEA Safeguards: Implementation at Nuclear Fuel Cycle Facilities. Safeguards Information Series 6. IAEA/SG/INF/6. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/1070/iaea-safeguards-implementation-at-nuclear-fuel-cycle-facilities.

IAEA. 1986. Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident. INSAG Series 1. Vienna: International Atomic Energy Agency. https://www.iaea.org/publications/3598/summary-report-on-the-post-accident-review-meeting-on-the-chernobyl-accident.

IAEA. 1989. Decontamination and Decommissioning of Nuclear Facilities (Final Report of Three Research Co-Ordination Meetings Held Between 1984 and 1987). TECDOC Series 511. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/766/decontamination-and-decommissioning-of-nuclear-facilities-final-report-of-three-research-co-ordination-meetings-held-between-1984-and-1987.

IAEA. 1992. Radioactive Waste Management: An IAEA Source Book, Non-serial Publications. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/3760/radioactive-waste-management-an-iaea-source-book.

IAEA. 1995. Principles of Radioactive Waste Management Safety Fundamentals. Safety Series 111-F. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/5192/principles-of-radioactive-waste-management-safety-fundamentals.

IAEA. 1996. Significant Incidents in Nuclear Fuel Cycle Facilities. TECDOC Series 867. Vienna, Austria: International Atomic Energy Agency. https://inis.iaea.org/collection/NCLCollectionStore/_Public/27/060/27060437.pdf.

IAEA. 1997. “Spent Fuel Management: Current Status and Prospects.” Nuclear Fuel Cycle and Materials Section. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/te_1006_prn.pdf.

IAEA. 1999a. Report on the Preliminary Fact Finding Mission Following the Accident at the Nuclear Fuel Processing Facility in Tokaimura, Japan. Non-Serial Publications. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/TOAC_web.pdf.

IAEA. 1999b. State of the Art Technology for Decontamination and Dismantling of Nuclear Facilities. Technical Reports Series 395. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/5783/state-of-the-art-technology-for-decontamination-and-dismantling-of-nuclear-facilities.

IAEA. 2002. “IAEA Safeguards Glossary—2001 Edition.” International Nuclear Verification Series No. 3. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/sites/default/files/iaea_safeguards_glossary.pdf.

IAEA. 2004a. “Management of Waste Containing Tritium and Carbon-14.” Technical Report Series No. 421. Vienna, Austria. International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/publications/PDF/TRS421_web.pdf.

IAEA. 2004b. “Operational and Decommissioning Experience with Fast Reactors.” Proceedings of a technical meeting. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/te_1405_web.pdf.

IAEA. 2005a. Thorium Fuel Cycle—Potential Benefits and Challenges. TECDOC Series 1450. Vienna: International Atomic Energy Agency. https://www.iaea.org/publications/7192/thorium-fuel-cycle-potential-benefits-and-challenges.

IAEA. 2005b. “Amendment to the Convention on the Physical Protection of Nuclear Material.” INFCIRC/274/Rev.1/Mod. 1. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/sites/default/files/publications/documents/infcircs/1979/infcirc274r1m1c.pdf.

IAEA. 2005c. “Status and Trends in Spent Fuel Reprocessing.” IAEA-TECDOC-1467. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/te_1467_web.pdf.

IAEA. 2006. Characterization, Treatment and Conditioning of Radioactive Graphite from Decommissioning of Nuclear Reactors. TECDOC Series 1521. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/7579/characterization-treatment-and-conditioning-of-radioactive-graphite-from-decommissioning-of-nuclear-reactors.

IAEA. 2007a. “Management of Reprocessed Uranium: Current Status and Future Prospects.” Nuclear Fuel Cycle and Materials Section. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/te_1529_web.pdf.

IAEA. 2007b. Radioactive Sodium Waste Treatment and Conditioning. TECDOC Series 1534. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/7642/radioactive-sodium-waste-treatment-and-conditioning.

IAEA. 2008. “Spent Fuel Reprocessing Options.” IAEA-TECDOC-1587. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/publications/PDF/te_1587_web.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

IAEA. 2009. “Use of Reprocessed Uranium: Challenges and Options.” Nuclear Energy Series No. NF-T-4.4. https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1411_web.pdf.

IAEA. 2011a. “Safeguards Techniques and Equipment: 2011 Edition.” International Nuclear Verification Series No. 1 (Rev. 2). Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/nvs1_web.pdf.

IAEA. 2011b. “Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities.” INFCIRC/225/Revision 5. IAEA Nuclear Security Series No. 13. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1481_web.pdf.

IAEA. 2011c. “Nuclear Security Recommendations on Radioactive Material and Associated Facilities.” Nuclear Security Series No. 14, Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1487_web.pdf.

IAEA. 2013a. “International Safeguards in Nuclear Facility Design and Construction.” IAEA Nuclear Energy Series, No. NF-T-2.8. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1600_web.pdf.

IAEA. 2013b. Legal and Institutional Issues of Transportable Nuclear Power Plants: A Preliminary Study. Nuclear Energy Series, NG-T-3.5. Vienna: International Atomic Energy Agency. https://www.iaea.org/publications/10516/legal-and-institutional-issues-of-transportable-nuclear-power-plants-a-preliminary-study.

IAEA. 2013c. Status of Fast Reactor Research and Technology Development. TECDOC Series 1691. Vienna: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/te_1691_web.pdf.

IAEA. 2014. International Safeguards in the Design of Nuclear Reactors. Nuclear Energy Series, NP-T-2.9. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/10710/international-safeguards-in-the-design-of-nuclear-reactors.

IAEA. 2015a. Status of Accelerator Driven Systems Research and Technology Development. TECDOC Series 1766. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/10870/status-of-accelerator-driven-systems-research-and-technology-development.

IAEA. 2015b. Security of Nuclear Material in Transport: Implementation Guide. IAEA Nuclear Security Series No. 26-G. https://www.iaea.org/publications/10792/security-of-nuclear-material-in-transpor. Accessed April 21, 2022.

IAEA. 2015c. “Security of Nuclear and Other Radioactive Material in Transport.” Version 2. Document Preparation Profile, NST053. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/sites/default/files/dpp_nst053_0.pdf.

IAEA. 2016a. “Functional Specifications for Nuclear Security Detection Equipment and Systems.” Document Preparation Profile NST059. Vienna, Austria: International Atomic Energy Agency, Version 1, April 1, 2016. https://www.iaea.org/sites/default/files/dpp_nst059.pdf.

IAEA. 2016b. “Development, Use and Maintenance of Threat Assessment and Design Basis Threat.” Document Preparation Profile, NST058. Vienna, Austria: International Atomic Energy Agency, Version 0, March 18, 2016. https://www.iaea.org/sites/default/files/dpp_nst058.pdf.

IAEA. 2017a. “International Safeguards in the Design of Fuel Fabrication Plants.” IAEA Nuclear Energy Series, No. NF-T-4.7. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1699_web.pdf.

IAEA. 2017b. “Safety of Nuclear Fuel Cycle Facilities.” No. SSR-4 Pub. 1791. IAEA Safety Standards for Protecting People and the Environment. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/PUB1791_web.pdf.

IAEA. 2018a. Decommissioning of Nuclear Power Plants, Research Reactors and Other Nuclear Fuel Cycle Facilities. Specific Safety Guides, SSG-47. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/12210/decommissioning-of-nuclear-power-plants-research-reactors-and-other-nuclear-fuel-cycle-facilities.

IAEA. 2018b. Physical Protection of Nuclear Material and Nuclear Facilities (Implementation of INFCIRC/225/Revision 5). Implementing Guides 27-G. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/11092/physical-protection-of-nuclear-material-and-nuclear-facilities-implementation-of-infcirc/225/revision-5.

IAEA. 2019a. “International Safeguards in the Design of Enrichment Plants.” IAEA Nuclear Energy Series, No. NF-T-4.10. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/PUB1865_web.pdf.

IAEA. 2019b. “International Safeguards in the Design of Reprocessing Plants.” IAEA Nuclear Energy Series, No. NF-T-3.2. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/publications/PDF/PUB1866_web.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

IAEA. 2019c. Security of Radioactive Material in Use and Storage and of Associated Facilities. Implementing Guides 11-G (Rev.1). Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/12360/security-of-radioactive-material-in-use-and-storage-and-of-associated-facilities.

IAEA. 2019d. “Identification and Categorization of Sabotage Targets, and Identification of Vital Areas at Nuclear Facilities.” Document Preparation Profile, NST063; Version 1.2, November 1. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/sites/default/files/dpp_nst063_1.pdf.

IAEA. 2019e. “Waste from Innovative Types of Reactors and Fuel Cycles: A Preliminary Study.” IAEA Nuclear Energy Series. Vienna, Austria: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/PUB1822_web.pdf.

IAEA. 2020a. Security of Radioactive Material in Transport. Implementing Guides 9-G (Rev. 1). Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/13400/security-of-radioactive-material-in-transport.

IAEA. 2020b. “The Safeguards Implementation Report for 2019.” GOV/2020/9. Safeguards Implementation Reports. Vienna, Austria: International Atomic Energy Agency. https://armscontrollaw.files.wordpress.com/2020/05/sir-2019.pdf.

IAEA. 2020c. Preventive and Protective Measures Against Insider Threats. Implementing Guides 8-G (Rev. 1). Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/12354/preventive-and-protective-measures-against-insider-threats.

IAEA. 2020d. Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges. TECDOC Series 1918. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/14697/lightwater-reactor-fuel-enrichment-beyond-the-five-per-cent-limit-perspectives-and-challenges.

IAEA. 2021a. National Nuclear Security Threat Assessment, Design Basis Threats and Representative Threat Statements. Implementing Guides 10-G (Rev. 1). Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/13618/national-nuclear-security-threat-assessment-design-basis-threats-and-representative-threat-statements.

IAEA. 2021b. Enhancing Nuclear Security Culture in Organizations Associated with Nuclear and Other Radioactive Material. Technical Guidance 38-T. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/13405/enhancing-nuclear-security-culture-in-organizations-associated-with-nuclear-and-other-radioactive-material.

IAEA. 2021c. “Communication Received from Certain Member States Concerning Their Policies Regarding the Management of Plutonium.” INFCIRC/549. Vienna, Austria: International Atomic IAEA. Energy, Electricity and Nuclear Power Estimates for the Period up to 2050. Reference Data Series 1. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/15028/energy-electricity-and-nuclear-power-estimates-for-the-period-up-to-2050.

IAEA. 2021d. Status and Trends in Pyroprocessing of Spent Nuclear Fuels. TECDOC Series 1967. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/publications/11062/status-and-trends-in-pyroprocessing-of-spent-nuclear-fuels.

IAEA. 2021e. Handbook on the Design of Physical Protection Systems for Nuclear Material and Nuclear Facility; Technical Guidance. IAEA Nuclear Security Series No. 40-T.

IAEA. 2021f. “Communication Received from France Concerning Its Policies Regarding the Management of Plutonium.” INFCIRC/549/Add.5/25. Statements on the Management of Plutonium and of High Enriched Uranium. Vienna, Austria: International Atomic Energy Agency. https://www.iaea.org/sites/default/files/publications/documents/infcircs/1998/infcirc549a5-25.pdf.

IAEA. 2022. “Live Chart of Nuclides.” IAEA Nuclear Data Section. https://www-nds.iaea.org/relnsd/vcharthtml/VChartHTML.html.

IAEA. n.d.-a. “The IAEA and the Non-Proliferation Treaty.” IAEA. https://www.iaea.org/topics/non-proliferation-treaty.

IAEA. n.d.-b. “Nuclear Security Series.” IAEA. https://www.iaea.org/resources/nuclear-security-series.

IAEA. n.d.-c. “Safeguards Agreements.” https://www.iaea.org/topics/safeguards-agreements. Accessed April 20, 2022.

IDEQ (Idaho Department of Environmental Quality). 1995. “1995 Settlement Agreement,” October 16. https://www2.deq.idaho.gov/admin/LEIA/api/document/download/14673.

Ignatiev, V., O. Feynberg, I. Gnidoi, A. Merzlyakov, A. Surenkov, V. Uglov, A. Zagnitko, V. Subbotin, I. Sannikov, A. Toropov, V. Afonichkin, A. Bovet, V. Khokhlov, V. Shishkin, M. Kormilitsyn, A. Lizin, and A. Osipenko. 2014. Molten salt actinide recycler and transforming system without and with Th–U support: Fuel cycle flexibility and key material properties. Annals of Nuclear Energy 64:408-420. https://doi.org/10.1016/j.anucene.2013.09.004.

IN2P3 (Institut National de Physique Nucléaire et Physique des Particules). n.d.-a. “Spent Fuel Composition.” https://www.radioactivity.eu.com/site/pages/Spent_Fuel_Composition.htm.

IN2P3. n.d.-b. “Long-Lived Fission Products.” https://www.radioactivity.eu.com/site/pages/Long_Lived_Fission_Products.htm.

INL (Idaho National Laboratory). 2021a. “INL’s Advanced Test Reactor.” Factsheet. Updated 2021. https://factsheets.inl.gov/FactSheets/Advanced%20Test%20Reactor%20--%20Safety.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

INL. 2021b. “Advanced Fuels Campaign Execution Plan.” Idaho Falls, ID: Idaho National Laboratory, July 29, 2021. https://www.osti.gov/biblio/1813552.

IPFM (International Panel on Fissile Materials). 2014. “Sweden Wants to Transfer Ownership of 834 kg of Separated Plutonium to the United Kingdom.” IPFM Blog. March 18. https://fissilematerials.org/blog/2014/03/sweden_wants_to_transfer_.html.

IPFM. 2020. “UK Sellafield Magnox Reprocessing Plant to Close in 2021, One Year Later Than Planned.” IPFM Blog. August 12, 2020. http://fissilematerials.org/blog/2020/08/uk_sellafield_magnox_repr.html.

IPFM. 2021. “Countries: India.” International Panel on Fissile Materials, August 31, 2021. https://fissilematerials.org/countries/india.html.

JAEA (Japan Atomic Energy Agency). n.d. “Reprocessing Technology Development.” Nuclear Fuel Cycle Engineering Laboratories. https://www.jaea.go.jp/english/04/tokai-cycle/02.htm.

JNFL (Japan Nuclear Fuel Limited). 2020 “MOX Fuel Fabrication.” December 16. https://www.jnfl.co.jp/en/business/mox.

JNFL. 2022. “Operation Plans for Rokkasho Reprocessing Plant and MOX Fuel Fabrication Plant.” Japan Nuclear Fuel Limited, February 10, 2022. https://www.jnfl.co.jp/en/release/press/2021/detail/20220210-1.html.

Johnson, S. 2009. “The Safeguards at Reprocessing Plants Under a Fissile Material (Cutoff) Treaty.” Research Report No. 6. Princeton, NJ: International Panel on Fissile Materials, February 2009. https://fissilematerials.org/library/rr06.pdf.

Johnstone, C. 2022. “French Regulator Quizzes EDF, Orano on Fuel Storage Capacity Limits,” Nucleonics Week, March 16.

Joly, P., and E. Boo. 2015. “Roadmap: Actinide Separation Processes 2015.” Safety of Actinide Separation Processes. European Commission.

Jorgensen, L. 2021. “ThorCon.” Presented at the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, January 11, 2021.

Kailas, S., M. Hemalatha, and A. Saxena. 2015. “Nuclear Transmutation Strategies for Management of Long-Lived Fission Products.” Pramana 85(3):517-523. September 1. https://doi.org/10.1007/s12043-015-1063-z.

Kairos. 2021. “Hermes Construction Permit Application Accepted for Review by Nuclear Regulatory Commission.” November 30, 2021. https://kairospower.com/external_updates/hermes-construction-permit-application-accepted-for-review-by-nuclear-regulatory-commission.

Kamide, H. 2021. “Overview of the Generation IV International Forum.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 28, 2021.

Katoh, Y., L. L. Snead, I. Szlufarska, and W. J. Weber. 2012. “Radiation Effects in SiC for Nuclear Structural Applications.” Material Challenges for Advanced Nuclear Power Systems 16(3):143-152. https://doi.org/10.1016/j.cossms.2012.03.005.

Kilochytska, T. 2021. “IAEA Designates New Collaborating Centre in France for Graphite Reactor Decommissioning.” International Atomic Energy Agency. September 30. https://www.iaea.org/newscenter/news/iaea-designates-newcollaborating-centre-in-france-for-graphite-reactor-decommissioning.

Kim, Y. I., S. J. Kim, Y. G. Kim, and Y. J. Kim. 1999. “Conceptual Design of KALIMER Uranium Metallic Fueled Core.” KAERI/TR-1279/99. Taejon, Republic of Korea: Korea Atomic Energy Research Institute. http://inis.iaea.org/search/search.aspx?orig_q=RN:46037652.

Kovacic, D. N., P. W. Gibbs, and L. M. Scott. 2020. “Model MC&A for Pebble Bed Reactors (Technical Direction No. 5 Task 2.6 Letter Report).” ORNL/SPR-2019/1329. Oak Ridge, TN: Oak Ridge National Laboratory. March 1. https://doi.org/10.2172/1606926.

Kovacic, D., P. Gibbs, L. Worrall, R. Hunneke, J. Harp, and J. Hu. 2021. “Advanced Reactor Safeguards: Nuclear Material Control and Accounting for Pebble Bed Reactors.” ORNL/SPR-2020-1849. Oak Ridge, TN: Oak Ridge National Laboratory. January. https://gain.inl.gov/SiteAssets/2021-April_SafeguardsAndSecurityWorkshop/Reading/Advanced%20 Reactor%20Safeguards%20-%20Nuclear%20Material%20Control%20and%20Accounting%20for%20Pebble%20 Bed%20Reactors.pdf.

Kozak, M., T. A. Feeney, C. D. Leigh, and H. W. Stockman. 1992. Performance assessment of the proposed disposal of depleted uranium as Class A Low-Level Waste, Sandia National Laboratories, Albuquerque, NM. www.nrc.gov/docs/ML1018/ML101890179.pdf.

Krahn, S. L., A. G. Croff, B. L. Smith, J. H. Clarke, A. G. Sowder, and A. J. Machiels. 2014. “Evaluating the Collective Radiation Dose to Workers from the U.S. Once-Through Nuclear Fuel Cycle.” Nuclear Technology 185(2):192-207. https://doi.org/10.13182/NT13-64.

Krall, L., T. McCartin, and A. Macfarlane. 2020. “Siting Deep Boreholes for Disposal of Radioactive Waste: Consequences for Tight Coupling between Natural and Engineered Systems.” Environmental Science & Technology 54(2):629-646. https://doi.org/10.1021/acs.est.9b03440.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Kramer, D. 2021. “Idaho project tests the limits of DOE aid to advanced reactors.” Physics Today. November. https://physicstoday.scitation.org/doi/10.1063/PT.3.4878.

Kramer, D. 2022. “DOE Prepares to Put a Nearly Completed Uranium Contract up for Bid.” Physics Today, February. https://doi.org/10.1063/PT.6.2.20220223a.

Krass, A. S., P. Boskma, B. Elzen, and W. A. Smit. 1983. Uranium Enrichment and Nuclear Weapon Proliferation. Milton Park, UK: Taylor and Francis.

Kumar, K.V. Suresh, A. Babu, B. Anandapadmanaban, and G. Srinivasan. 2011. “Twenty Five Years of Operating Experience with the Fast Breeder Test Reactor.” Asian Nuclear Prospects 2010 7(January 1):323-332. https://doi.org/10.1016/j.egypro.2011.06.042.

LaHaye, N. L., and D. E. Burkes. 2019. “Metal Fuel Fabrication Safety and Hazards.” Richland, WA: Pacific Northwest National Laboratory. June. https://www.nrc.gov/docs/ML1919/ML19193A057.pdf.

Landais, P. 2021. “France’s Strategy on the Back-End of the Fuel Cycle and the Management and Disposal of Radioactive Waste: Is Final Disposal Still the Achilles’ Heel of the Nuclear Industry?” Presented at the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 29. https://www.nationalacademies.org/event/09-28-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-10-september-28-29-2021-public-sessions.

Larsen, R. K. 2021. “Aspects of Material Accounting and Control for Advanced Reactors.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, May 17, 2021. https://www.nationalacademies.org/event/05-17-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-may-17-19-2021-meeting.

Larson, L. N. 2019. “The Front End of the Nuclear Fuel Cycle: Current Issues.” Washington, DC: Congressional Research Service. July 29. https://fas.org/sgp/crs/nuke/R45753.pdf.

Larson, L. N. 2020. “Uranium Reserve Program Proposal: Policy Implications.” Washington, DC: Congressional Research Service. April 16. https://sgp.fas.org/crs/nuke/IF11505.pdf.

Latkowski, J. 2021. “TerraPower’s Molten Chloride Fast Reactor (MCFR).” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, February 22, 2021. https://www.nationalacademies.org/event/02-22-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-february-22-and-23-2021-meeting.

LeadCold. 2021. “Breakthrough Innovation.” https://www.leadcold.com/technology.html. Accessed December 28, 2021.

LeBlanc, D. 2010. “Denatured Molten Salt Reactors (DMSR): An Idea Whose Time Has Finally Come?” Atoms for Power, Health and the Environment 31st annual conference of the Canadian Nuclear Society and 34th annual conference of the Canadian Nuclear Society and Canadian Nuclear Association. Canada: Canadian Nuclear Society. https://twugbcn.files.wordpress.com/2011/03/1-d_leblanc_ovrvw_denmsr.pdf.

LeBlanc, D. 2021. “Leading the Way to a Bright Energy Future: Overview of the IMSR.” Presented at the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, online, January 11. https://www.nationalacademies.org/event/01-11-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-january-11-2021-and-january-13-2021-meeting.

Lee, J. C. 2020. Nuclear Reactor: Physics and Engineering. Hoboken, NJ: John Wiley and Sons.

Lee, W. E., M. Gilbert, S. T. Murphy, and R. W. Grimes. 2013. “Opportunities for Advanced Ceramics and Composites in the Nuclear Sector.” Journal of the American Ceramic Society 96(7):2005-2030. https://doi.org/10.1111/jace.12406.

Les Échos. 2016. “Nucléaire: les arrêts de réacteur vont couter 1 milliard d’euros à EDF en 2016.” www.lesechos.fr/2016/11/nucleaire-les-arrets-de-reacteur-vont-couter-1-milliard-deurosa-edf-en-2016-225670.

Liu, D., S. Knol, J. Ell, H. Barnard, M. Davies, J. A. Vreeling, and R. O. Ritchie. 2020. “X-Ray Tomography Study on the Crushing Strength and Irradiation Behaviour of Dedicated Tristructural Isotropic Nuclear Fuel Particles at 1000°C.” Materials and Design 187(February 1):108382. https://doi.org/10.1016/j.matdes.2019.108382.

Lommers, L. 2021. “Framatome Steam Cycle High-Temperature Gas-Cooled Reactors.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, February 22, 2021. https://www.nationalacademies.org/event/02-22-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-february-22-and-23-2021-meeting.

Long, J. T. 1967. Engineering for Nuclear Fuel Reprocessing. New York: Gordon and Breach Science Publishers.

Machiels, A., S. Massara, and C. Garzenne. 2009. “Dynamic Analysis of Deployment Scenario of Faster Burner Reactors in the U.S. Nuclear Fleet.” GLOBAL 2009, Paris, France.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Magill, J., V. Berthou, D. Haas, J. Galy, R. Schenkel, H.-W. Wiese, G. Heusener, J. Tommasi, G. Youinou. 2003. Impact Limits of Partitioning and Transmutation Scenarios on Radiotoxicity of Actinides in Radioactive Waste. Nuclear Energy 42:263-277. https://www.researchgate.net/profile/J-Tommasi/publication/252069412_Impact_Limits_of_Partitioning_and_Transmutation_Scenarios_on_Radiotoxicity_of_Actinides_in_Radioactive_Waste/links/0f31752e0c63d46953000000/Impact-Limits-of-Partitioning-and-Transmutation-Scenarios-on-Radiotoxicity-of-Actinides-in-Radioactive-Waste.pdf.

Mahanty, B., A. S. Kanekar, S. A. Ansari, A. Bhattacharyya, and P. K. Mohapatra. 2019. “Separation of Neptunium from Actinides by Monoamides: A Solvent Extraction Study.” Radiochimica Acta 107(5):369-376. https://doi.org/10.1515/ract-2018-3074.

Majumdar, D., S. N. Jahshan, C. M. Allison, P. Kuan, and T. R. Thomas. 1992. “Recycling of Nuclear Spent Fuel with AIROX Processing.” DOE/ID-10423. Idaho Falls, ID: U.S. Department of Energy. December 1. https://doi.org/10.2172/10146308.

Malherbe, J. B. 2013. “Diffusion of Fission Products and Radiation Damage in SiC.” Journal of Physics D: Applied Physics 46(47):473001. https://doi.org/10.1088/0022-3727/46/47/473001.

Mallapaty, S. 2021. “China Prepares to Test Thorium-Fuelled Nuclear Reactor.” Nature, September 10, 2021. https://www.nature.com/articles/d41586-021-02459-w.

Martin, G., M. Guyot, F. Laugier, G. Senentz, G. Krivtchik, B. Carlier, D. Lecarpentier, F. Descamps, C. Chabert, and R. Eschbach. 2018. “French Scenarios Toward Fast Plutonium Multi-Recycling in PWR.” ICAPP, Charlotte, United States. ffcea-01908271. https://hal-cea.archives-ouvertes.fr/cea-01908271/document. Accessed April 20, 2022.

McFarlane, J. 2021. “Hazards Associated with Molten Salt Reactor Systems.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors. October 15. https://www.nationalacademies.org/event/10-14-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-11-public-sessions-october-14-15-2021.

McFarlane, J., P. A. Taylor, D. E. Holcomb, and W. Poore III. 2019. “Review of Hazards Associated with Molten Salt Reactor Fuel Processing Operations.” United States. https://doi.org/10.2172/1543201.

McFarlane, J., B. J. Riley, D. E. Holcomb, A. Lines, H. B. Andrews, S. A. Bryan, A.S. Chapel, N. D. B. Ezell, H. M. Felmy, M. S. Greenwood, P. W. Humrickhouse, and K. G. Myhre. 2020. “Molten Salt Reactor Engineering Study for Off-Gas Management: Nuclear Technology Research and Development.” ORNL/TN-2020/1602, PNNL-30159. August 31. https://info.ornl.gov/sites/publications/Files/Pub142799.pdf. Accessed April 20, 2022.

McMillan, B. 2019. “Molten Salt Reactor Experiment Project Initiatives.” Oak Ridge Office of Environmental Management. https://www.energy.gov/sites/prod/files/2019/11/f68/ORSSAB%20MSRE%20Presentation%20-%20Nov%202019.pdf. Accessed April 21, 2022.

METI (Ministry of Economy, Trade, and Industry). 2016. “Spent Nuclear Fuel Reprocessing Implementation Act.” METI. October 20, 2016. https://www.meti.go.jp/english/policy/energy_environment/law/index.html.

Metlay, D. S. 2016. “Selecting a Site for a Radioactive Waste Repository: A Historical Analysis.” Elements 12:269-274. https://doi.org/DOI: 10.2113/gselements.12.4.269.

Metlay, D. S. 2021. “Social Acceptability of Geologic Disposal.” In Encyclopedia of Nuclear Energy, edited by E. Greenspan, pp. 684-697. Oxford, UK: Elsevier. https://doi.org/10.1016/B978-0-12-819725-7.00157-4.

Miguirditchian, M., and R. Taylor. 2021. “The Adaptation of Recycling Processes to Pu-Multi Recycling.” In Encyclopedia of Nuclear Energy, edited by E. Greenspan, pp. 523-533. Oxford, UK: Elsevier. https://doi.org/10.1016/B978-0-12-819725-7.00228-2.

Miguirditchian, M., S. Grandjean, C. Sorel, V. Vanel, T. Delahaye, S. Pillon, L. Ramond, et al. 2017. “Advanced Concepts for Uranium and Plutonium Multi-Recycling.” In GLOBAL 2017 International Nuclear Fuel Cycle Conference. Seoul, South Korea. https://hal.archives-ouvertes.fr/hal-02418116.

Miles, B. 2016. “Naval Spent Fuel Transportation.” Nuclear Waste Technical Review Board Meeting presented at the Summer 2016 Board Meeting, Washington, DC, August 24. https://www.nwtrb.gov/docs/default-source/meetings/2016/august/miles.pdf?sfvrsn=12.

MIT (Massachusetts Institute of Technology). 2003. “The Future of Nuclear Power: An Interdisciplinary MIT Study.” Cambridge, MA: Massachusetts Institute of Technology. https://web.mit.edu/nuclearpower/pdf/nuclearpower-full.pdf.

MIT. 2009. “Update of the MIT 2003 Future of Nuclear Power: An Interdisciplinary MIT Study.” Cambridge, MA: Massachusetts Institute of Technology. https://web.mit.edu/nuclearpower/pdf/nuclearpower-update2009.pdf.

MIT. 2011. “The Future of the Nuclear Fuel Cycle.” Cambridge, MA: Massachusetts Institute of Technology, 2011. https://energy.mit.edu/wp-content/uploads/2011/04/MITEI-The-Future-of-the-Nuclear-Fuel-Cycle.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

MIT. 2018. “The Future of Nuclear Energy in a Carbon-Constrained World: An Interdisciplinary MIT Study.” Cambridge, MA: Massachusetts Institute of Technology. http://energy.mit.edu/wp-content/uploads/2018/09/The-Future-of-Nuclear-Energy-in-a-Carbon-Constrained-World.pdf. MIT Energy Initiative

Moltex Energy. 2021. “Moltex Completes Phase 1 of CNSC Vendor Design Review.” Moltex Energy, May 25, 2021. https://www.moltexenergy.com/moltex-completes-phase-1-of-cnsc-vendor-design-review.

Moltex Energy. 2022. “FAQ.” Moltex Energy. https://www.moltexenergy.com/faq.

Moore, E. N., and T. F. Severynse. 2020. “Conceptual Assessment of VTR Add-on Processing Capability.” Aiken, SC: Savannah River National Laboratory. July 6. https://web.archive.org/web/20201105184215id_/https://sti.srs.gov/fulltext/SRNL-TR-2020-00171_R1.pdf.

Moorman, R. 2008. “A Safety Re-evaluation of the AVR Pebble Bed Reactor Operation and Its Consequences for Future HTR Concepts.” Berichte des Forschungszentrum Jülich 4275. https://juser.fz-juelich.de/record/1304/files/Juel_4275_Moormann.pdf?version=1.

Morris, E. E., and T. H. Bauer. 2005. “Modeling of the Repository Behavior of TRISO Fuel (Milestone 4295 for Work Package A0403K11: Rev.1).” Argonne, IL: Argonne National Laboratory, September 29. https://publications.anl.gov/anlpubs/2006/01/55330.pdf.

Mulder, E. J. 2021. “Overview of X-Energy’s 200 MWth Xe-100 Reactor.” Presentation to the National Academy of Sciences Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, January 13. https://www.nationalacademies.org/event/01-11-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-january-11-2021-and-january-13-2021-meeting.

Murray, R. L., and K. E. Holbert. 2014. Nuclear Energy: An Introduction to the Concepts, Systems, and Applications of Nuclear Processes. 7th ed. Boston. MA: Butterworth-Heinemann.

Murray, R. L., and K. E. Holbert. 2020. “Nuclear Power Plants.” In Nuclear Energy: An Introduction to the Concepts, Systems, and Applications of Nuclear Processes, 8th Edition, pp. 325-348. Cambridge, MA: Elsevier. https://www.sciencedirect.com/science/article/pii/B9780128128817000186?via%3Dihub.

Nabielek, H., H. van der Merwe, J. Fachinger, K. Verfondern, W. von Lensa, B. Grambow, and E. de Visser-Tynova. 2009. “Ceramic Coated Particles for Safe Operation in HTRs and in Long-Term Storage.” In Ceramic Engineering and Science Proceedings 30:193-202. Daytona Beach, FL. https://doi.org/10.1002/9780470584002.ch17.

Nagley, S. 2020. “BWXT HA-LEU Supply (Enrichment, De-Conversion, Fuel Fab, and Transportation).” Presented at the HALEU Webinar, April 28. https://gain.inl.gov/HALEU_Webinar_Presentations/12-Nagley,BWXT-28Apr2020.pdf.

Nagy, K., J. L. Kloosterman, D. Lathouwers, and T. H. J. J. van der Hagen. 2008. “Parametric Studies on the Fuel Salt Compositions in Thermal Molten Salt Breeder Reactors.” International Conference on the Physics of Reactors, Interlaken, Switzerland, September 14-19.

Napier, B. A. 2020. “Non-LWR Fuel Cycle Environmental Data.” PNNL29367 Rev. 1. Richland, WA: Pacific Northwest National Laboratory. March. https://www.nrc.gov/docs/ML2007/ML20076G075.pdf.

NAS (National Academy of Sciences). 1994. Management and Disposition of Excess Weapons Plutonium. Washington, DC: National Academy Press. https://doi.org/10.17226/2345.

NASEM (National Academies of Sciences, Engineering, and Medicine). 2020. Review of the Department of Energy’s Plans for Disposal of Surplus Plutonium in the Waste Isolation Pilot Plant. Washington, DC: The National Academies Press. https://doi.org/10.17226/25593.

Nash, K. L., and G. J. Lumetta. 2011. Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment. Oxford, UK: Woodhouse Publishing Ltd.

National Research Council. 1996. Nuclear Wastes: Technologies for Separations and Transmutation. Washington, DC: National Academy Press. https://doi.org/10.17226/4912.

National Research Council. 2000. Electrometallurgical Techniques for DOE Spent Fuel Treatment. Washington, DC: National Academy Press. https://doi.org/10.17226/9883.

National Research Council. 2005. Monitoring Nuclear Weapons and Nuclear-Explosive Materials: An Assessment of Methods and Capabilities. Washington, DC: The National Academies Press. https://doi.org/10.17226/11265.

National Research Council. 2008. Review of DOE’s Nuclear Energy Research and Development Program. Washington, DC: The National Academies Press. https://doi.org/10.17226/11998.

National Research Council. 2012. Analysis of Cancer Risks in Populations Near Nuclear Facilities: Phase 1. Washington, DC: The National Academies Press. https://doi.org/10.17226/13388.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

NEA and IAEA (Nuclear Energy Agency and International Atomic Energy Agency). 2020. “Uranium 2020: Resources, Production, and Demand.” Nuclear Energy Agency, 2020. https://www.oecd-nea.org/jcms/pl_52718/uranium-2020-resources-production-and-demand.

NEA-OECD (Nuclear Energy Agency–Organisation for Economic Co-operation and Development). 1994. “The Economics of the Nuclear Fuel Cycle.” Paris, France: Nuclear Energy Agency. https://www.oecd-nea.org/upload/docs/application/pdf/2020-07/the_economics_of_the_nuclear_fuel_cycle_1994.pdf.

NEA-OECD. 2002. “Accelerator-driven Systems (ADS) and Fast Reactors (FR).” In Advanced Nuclear Fuel Cycles, A Comparative Study.” Paris, France. Nuclear Energy Agency. https://www.oecd-nea.org/ndd/reports/2002/nea3109-ads.pdf.

NEA-OECD. 2005. “The Safety of the Nuclear Fuel Cycle.” NEA No. 3588. Nuclear Safety. Paris, France: Nuclear Energy Agency. https://doi.org/10.1787/9789264014220-en.

NEA-OECD. 2006a. “Forty Years of Uranium Resources, Production, and Demand in Perspective: ‘The Red Book Retrospective.’” NEA No. 6096. Paris, France: Organisation for Economic Co-Operation and Development. https://www.oecd-nea.org/jcms/pl_14100/forty-years-of-uranium-resources-production-and-demand-in-perspective?details=true.

NEA-OECD. 2006b. “Advanced Nuclear Fuel Cycles and Radioactive Waste Management.” Nuclear Development. Paris, France: Nuclear Energy Agency, 2006. https://www.oecd-nea.org/upload/docs/application/pdf/2019-12/5990-advanced-nfc-rwm.pdf.

NEA-OECD. 2012. “Homogeneous versus Heterogeneous Recycling of Transuranics in Fast Nuclear Reactors.” NEA No. 7077. Nuclear Science. Paris, France: Organisation for Economic Co-Operation and Development, 2012. https://www.oecd-nea.org/jcms/pl_14790/homogeneous-versus-heterogeneous-recycling-of-transuranics-in-fast-nuclear-reactors?details=true.

NEA-OECD. 2013. “The Economics of the Back End of the Nuclear Fuel Cycle.” Nuclear Development. Boulogne-Billancourt, France: Nuclear Energy Agency, 2013. https://www.oecd-nea.org/upload/docs/application/pdf/2019-12/7061-ebenfc.pdf.

NEA-OECD. 2015a. “Introduction of Thorium in the Nuclear Fuel Cycle: Short- to Long-Term Considerations.” NEA No. 7224. Nuclear Science. Paris: Nuclear Energy Agency. https://www.oecd-nea.org/upload/docs/application/pdf/2019-12/7224-thorium.pdf.

NEA-OECD. 2015b. “Perspectives on the Use of Thorium in the Nuclear Fuel Cycle: Extended Summary.” NEA No. 7728. Nuclear Science. Paris, France: Organisation for Economic Co-Operation and Development. https://www.oecd-nea.org/upload/docs/application/pdf/2019-12/7228-thorium-es.pdf.

NEA-OECD. 2018a. Tests and Research Reactor Capabilities for Nuclear Fuel and Material Studies. Background Paper for the Workshop “Building Multinational Fuel and Materials Testing Capacities for Science, Safety and Industry.” OECD Conference Center, Boulogne-Billancourt. 4-5 October. https://www.oecd-nea.org/science/workshops/fuelmat2018/documents/BackgroundPaperWorkshopOct4-528_09_2018.pdf.

NEA-OECD. 2018b. “State-of-the-Art Report on the Progress of Nuclear Fuel Cycle Chemistry.” Nuclear Science. Boulogne-Billancourt, France: Nuclear Energy Agency. https://www.oecd-nea.org/jcms/pl_14970/state-of-the-art-report-on-the-progress-of-nuclear-fuel-cycle-chemistry.

NEA-OECD. 2019. “A Code-to-Code Benchmark for High-Temperature Gas-Cooled Reactor Fuel Element Depletion.” NEA/NSC/R(2019)1. Paris, France: Nuclear Energy Agency, February 2019. https://www.oecd-nea.org/science/wprs/egrpans/documents/nsc-r2019-1.pdf.

NEA-OECD. 2020. “Management and Disposal of High-Level Radioactive Waste: Global Progress and Solutions.” NEA No. 7532. Radioactive Waste Management. Paris, France: Nuclear Energy Agency. https://www.oecd-nea.org/rwm/pubs/2020/7532-DGR.pdf.

NEA-OECD. 2021. “Strategies and Considerations for the Back End of the Fuel Cycle.” Nuclear Technology Development and Economics. Boulogne-Billancourt, France: Nuclear Energy Agency. https://www.oecd-nea.org/jcms/pl_55928/strategies-and-considerations-for-the-back-end-of-the-fuel-cycle?details=true.

NEA-OECD. n.d. “Nuclear Innovation 2050 (NI2050).” Nuclear Energy Agency. https://www.oecd-nea.org/jcms/pl_21829/nuclear-innovation-2050-ni2050. Accessed March 14, 2022.

NEI (Nuclear Engineering International). 2017. “Russia Looks to Develop Environmentally Friendly Reprocessing.” Nuclear Engineering International. November 29. https://www.neimagazine.com/news/newsrussia-looks-to-develop-environmentally-friendly-reprocessing-5989047.

NEI. 2020a. “US and Russia Sign Final Amendment to Uranium Suspension Agreement.” Nuclear Engineering International. October 8. https://www.neimagazine.com/news/newsus-and-russia-sign-final-amendment-to-uranium-suspension-agreement-8172402.

NEI. 2020b. “Japan’s Rokkasho Reprocessing Plant Postponed Again.” Nuclear Engineering International. August 27. https://www.neimagazine.com/news/newsjapans-rokkasho-reprocessing-plant-postponed-again-8105722.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

NEI. 2021a. “Terrestrial Upgrades Molten Salt Reactor Design.” September 16. https://www.neimagazine.com/news/newsterrestrial-upgrades-molten-salt-reactor-design-9086577.

NEI. 2021b. “First Remix Fuel Assemblies Loaded at Russia’s Balakovo Nuclear Plant.” Nuclear Engineering International. December 23. https://www.neimagazine.com/news/newsfirst-remix-fuel-assemblies-loaded-at-russias-balakovo-nuclear-plant-9343328.

NEI. 2022. “Vogtle NPP Faces More Possible Delays.” Nuclear Engineering International. August 3, 2022. https://www.neimagazine.com/news/newsvogtle-npp-faces-more-possible-delays-9897168.

Neider, T. 2021. “Natrium.” Presented at the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, February 22. https://www.nationalacademies.org/event/02-22-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-february-22-and-23-2021-meeting.

Newton, F., and N. Kolosovskaya. 2020. “HALEU: Rosatom View.” Presented at the HALEU Webinar, April 28. https://gain.inl.gov/HALEU_Webinar_Presentations/14-15-Newton-Kolosovskaya,TENEX-28Apr2020.pdf.

Nichol, M. 2021. Current Status of Advanced Nuclear Reactors. Presentation given to the NC Energy Policy Council. August 18, 2021. https://files.nc.gov/ncdeq/energy-policy-council/August_18_2021_EPC_Meeting.pdf

NPT (Treaty on the Non-Proliferation of Nuclear Weapons). 1968. https://www.state.gov/wp-content/uploads/2019/03/228-Nuclear-Nonproliferation-Treaty-508.pdf.

NRC (National Research Council). 1957. The Disposal of Radioactive Waste on Land. Washington, DC: National Academy Press. https://doi.org/10.17226/10294.

NSUF (Nuclear Science User Facilities). n.d. “NSUF Facilities and Foreign Affiliates.” Nuclear Science User Facilities. https://nsuf.inl.gov/Home/PartnerFacilities. Accessed July 29, 2022.

Nuclear Decommissioning Collaborative. 2022. “Trojan.” The Nation’s Decommissioning Clearinghouse. 2022. https://decommissioningcollaborative.org/trojan/.

Nuclear Energy Institute. 2018. “Addressing the Challenges with Establishing the Infrastructure for the Front-End of the Nuclear Fuel Cycle for Advanced Reactors.” Washington, DC: Nuclear Energy Institute. January. https://www.nrc.gov/docs/ML1810/ML18103A250.pdf.

NuclearSAFE. 2018. “Technology.” https://nstusa.net/technology.

NuScale Power. 2020. “NuScale Final Safety Analysis Report, Chapter 4: Reactor.” ML20224A492. NuScale Standard Plant Design Certification Application. NuScale Power. https://www.nrc.gov/docs/ML2022/ML20224A492.pdf.

NuScale Power. 2022a. “Overview of Design Optimization Process for a Commercial Nuclear Core.” NuScale Power, August 26, 2022.

NuScale Power. 2022b. NuScale Response to the National Academies of Sciences, Engineering, and Medicine Questionnaire, NuScale Power, WP-120652, Rev. A, June 22, 2022.

Nutt, M. 2021. “Advanced Non-Light Water Reactors: Integrated Waste Management System Considerations.” Presented at the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, online, December 16. https://www.nationalacademies.org/event/12-16-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-13-december-16-2021.

NWTRB (Nuclear Waste Technical Review Board). 2015. “Designing a Process for Selecting a Site for a Deep-Mined, Geologic Repository for High-Level Radioactive Waste and Spent Nuclear Fuel: A Detailed Analysis.” Report to the U.S. Congress and Secretary of Energy. Arlington, VA: U.S. Nuclear Waste Technical Review Board, November 2015. https://www.nwtrb.gov/docs/default-source/reports/siting_report_analysis.pdf?sfvrsn=9.

NWTRB. 2017. “Management and Disposal of U.S. Department of Energy Spent Nuclear Fuel: A Report to the United States Congress and the Secretary of Energy.” Arlington, VA: U.S. Nuclear Waste Technical Review Board. December. https://www.nwtrb.gov/docs/default-source/reports/nwtrb-mngmntanddisposal-dec2017-508a.pdf?sfvrsn=12.

NWTRB. 2020. “Department of Energy-Managed Spent Nuclear Fuel at the Hanford Site.” U.S. Nuclear Waste Technical Review Board. June. https://www.nwtrb.gov/docs/default-source/facts-sheets/doe-snf-fact-sheet---hanford-rev-1.pdf?sfvrsn=8.

Nygaard, E. 2021. “BWXT’s Advanced Nuclear Reactor (BANR).” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors. January 11. https://www.nationalacademies.org/event/01-11-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-january-11-2021-and-january-13-2021meeting.

Okada, K. 1985. “Separation Method for a Spent Fuel Rod.” European Patent, Application No. 19850302514.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Oklo. 2020. “Combined Operating License Application, Part V: Non-Applicabilities and Requested Exemptions.” OkloPower2020-PartV-NP, Rev. 0. Oklo, Inc. https://www.nrc.gov/docs/ML2007/ML20075A006.pdf.

Olson, G. L., R. K. McCardell, and D. B. Illum. 2002. “Fuel Summary Report: Shippingport Light Water Breeder Reactor—Rev. 2.” INEEL/EXT-98-00799. Idaho Falls, ID: Idaho National Engineering and Environmental Laboratory. September 1. https://doi.org/10.2172/910649.

Orano. 2021a. “MOX, Recycling Nuclear Energy.” https://www.orano.group/country/china/en/our-stories/mox-recycling-nuclear-energy.

Orano. 2021b. “Orano’s activity in China.” https://www.orano.group/en/orano-across-the-world/china#OranoactivityinChina. Accessed August 5, 2021.

Orano. n.d. “Orano La Hague.” https://www.orano.group/country/china/en/our-stories/orano-la-hague. Accessed February 22, 2022.

Oregon DOE (Department of Energy). n.d. “Trojan Nuclear Site Spent Fuel Storage.” Oregon.gov. https://www.oregon.gov/energy/safety-resiliency/pages/trojan-site.aspx. Accessed December 1, 2021.

O’Sullivan, R. 2021. “Moltex Technology.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, February 23, 2021. https://www.nationalacademies.org/event/02-22-2021/merits-and-viability-of-different-nuclear-fuel-cycles-andtechnology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-february-22-and-23-2021-meeting.

OTA (Office of Technology Assessment). 1977. “Nuclear Proliferation and Safeguards.” NTIS order #PB-275843. Washington, DC: Office of Technology Assessment, June 1977. https://ota.fas.org/reports/7705.pdf.

Pappano, P. 2021. “X-Energy TRISO Fuel Production.” Presented at the National Academies’ Committee on the Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors, February 23.

Patel, S. 2019. “France Scraps Fast Nuclear Reactor Demonstration.” POWER, November 1, 2019. https://www.powermag.com/france-scraps-fast-nuclear-reactor-demonstration.

Patel, S. 2021. “Honeywell to Reopen Sole U.S. Uranium Conversion Plant.” POWERnews, February 9. https://www.powermag.com/honeywell-to-reopen-sole-u-s-uranium-conversion-plant.

Patel, S. 2022. “Nuclear Field Activities Completed for Idaho NuScale SMR Project.” POWERnews, February 3. https://www.powermag.com/nuclear-field-activities-completed-for-idaho-nuscale-smr-project.

Patterson, M. N. 2021. “Update on EBR-II Used Fuel Treatment.” INL/EXT-21-64586. Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 29, 2021. https://www.nationalacademies.org/event/09-28-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-10-september-28-29-2021-public-sessions.

Paunov, P., and I. Naydenov. 2020. “Long-Term Radiotoxicity Evaluation of PWR Spent Uranium and MOX Fuel and Highly Active Waste.” E3S Web of Conferences. 207. https://doi.org/10.1051/e3sconf/202020701024.

Paviet-Hartmann, P., G. Cerefice, M. Stacey, and S. Bakhtiar. 2011. “Analysis of Nuclear Proliferation Resistance Reprocessing and Recycling Technologies.” In Report Number: INL/CON-10-20124. Makuhari, Japan. https://www.osti.gov/biblio/1023498.

Pereira, C. 2020. “Molten Salt Reactor Recycle Option.” Presented at the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, December 8. https://www.nationalacademies.org/event/12-07-2020/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-december-7-8-2020-meeting.

Peretz, F. J., J. E. Rushton, R. L. Faulkner, K. L. Walker, and G. D. Del Cul. 1998. “Removal of Uranium and Salt from the Molten Salt Reactor Experiment.” ORNL/CP-98146. Oak Ridge, TN: Oak Ridge National Laboratory.

Perry, R. 2019. “Energy Secretary’s Report to Congress Regarding Atomic Energy Defense Act (50 U.S.C. Section 2566).” April 23. https://nuke.fas.org/guide/usa/mox-rept-2019.pdf.

Peters, M. T., and R. C. Ewing. 2007. “A Science-Based Approach to Understanding Waste Form Durability in Open and Closed Nuclear Fuel Cycles.” E-MRS 2006: Symposium N 362 (2, May 31):395-401. https://doi.org/10.1016/j.jnucmat.2007.01.085.

Peters, S., D. Vinson, and J. T. Carter. 2020. “Spent Nuclear Fuel and Reprocessing Waste Inventory.” U.S. Department of Energy, September 2020. https://sti.srs.gov/fulltext/FCRD-NFST-2013-000263_R7.pdf.

Peterson, J., and M. L. Dunzik-Gougar. 2011. “Modeling Spent TRISO Fuel for Geological Disposal: Corrosion and Failure Under Oxidizing Conditions in the Presence of Water.” Progress in Nuclear Energy 53(3):278-284. https://doi.org/10.1016/j.pnucene.2010.12.003.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Peterson, J., and J. Wagner. 2014. “Characteristics of Commercial Spent Nuclear Fuel: Distributed, Diverse, and Changing with Time.” Radwaste Solutions January-March:50-59.

Petti, D., R. Hill, J. Gehin, H. Gougar, G. Strydom, F. Heidet, J. Kinsey, C. Grandy, A. Qualls, N. Brown, J. Powers, E. Hoffman, and D. Croson. 2017. “Advanced Demonstration and Test Reactor Options Study.” Idaho Falls, ID: Idaho National Laboratory. January.

Pierce, R. A. 2017. Low temperature chemical processing of graphite-clad nuclear fuels. 9,793,019. Aiken, SC, issued October 17. https://patft.uspto.gov/netacgi/nph-Parser?Sect1=PTO1&Sect2=HITOFF&d=PALL&p=1&u=%2Fnetahtml%2FPTO%2Fsrchnum.htm&r=1&f=G&l=50&s1=9793019.PN.&OS=PN/9793019&RS=PN/9793019.

Piet, S. J. 2013. “When Is the Simple Radiotoxicity Approach Useful for Advanced Fuel Cycle System Assessments Given the Existence of Complex Performance Dose Assessments?” Nuclear Science and Engineering 173(1, January 1):58-81. https://doi.org/10.13182/NSE11-114.

Podvig, P. 2021. “Russia’s Efforts to Develop Advanced Nuclear Cycles.” Presented at the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 15. https://www.nationalacademies.org/event/09-13-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-9-september-13-15-2021.

Poinssot, C. 2021. “What Are the Advantages and Drawbacks of Recycling Spent Nuclear Fuels, and Why Recycling Can Be a Significant Contribution to Sustainable Nuclear Energy Systems?” White Paper for National Academies’ Committee on the Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors, 2021.

Poinssot, C., and B. Boullis. 2012. “Actinide Recycling within Closed Fuel Cycles.” Nuclear Engineering International, February 14. https://www.neimagazine.com/features/featureactinide-recycling-within-closed-fuel-cycles.

Poinssot, C., B. Boullis, J.-M. Adnet, and E. Touron. 2017a. From the Bataille’s Law to the Am-recycling integral experiments, overview of 25 years of R&D in CEA on Minor Actinides Partitioning Processes. GLOBAL 2017, September, Seoul, South Korea. https://hal.science/cea-02434525.

Poinssot, C., S. Grandjean, S. Bourg, J. Serp, E. Touron, and B. Boullis. 2017b. French Perspective on the Respective Interests of Hydro- and Pyro-Chemical Processes for Recycling Future Spent Nuclear Fuels. GLOBAL 2017, September, Seoul, South Korea. https://hal.science/cea-02434536.

Poneman, D., and Cutlip, L. 2021. “Status and Prospects for HALEU Production in the United States.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, June 2. https://www.nationalacademies.org/event/06-01-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-6-part-1-june-1-2-2021.

Postovarova, D. V., N. V. Kovalev, M. S. Onegin, and B. A. Bibichev. 2016. “Radiation Characteristics of REMIX Fuel During Multiple Recycling in VVER-1000 Reactors.” Nuclear Energy and Technology 2(2, June 1):119-125. https://doi.org/10.1016/j.nucet.2016.05.009.

Prabhu, D. R., G. R. Mahajan, and G. M. Nair. 1997. “Di(2-Ethyl Hexyl) Butyramide and Di(2-Ethyl Hexyl)Isobutyramide as Extractants for Uranium(VI) and Plutonium(IV).” Journal of Radioanalytical and Nuclear Chemistry 224(1):113-117. https://doi.org/10.1007/BF02034622.

Ramana, M. V., and E. Saikawa. 2011. “Choosing a Standard Reactor: International Competition and Domestic Politics in Chinese Nuclear Policy.” Energy 36(12, December 1):6779-6789. https://doi.org/10.1016/j.energy.2011.10.022.

Reagan, R. 1981. “Statement Announcing a Series of Policy Initiatives on Nuclear Energy.” https://www.reaganlibrary.gov/archives/speech/statement-announcing-series-policy-initiatives-nuclear-energy.

Rechard, R. P., T. Hadgu, Y. Wang, L. C. Sanchez, P. McDaniel, C. Skinner, N. Fathi, S. Frank, and M. Patterson. 2017. “Feasibility of Direct Disposal of Salt Waste from Electrochemical Processing of Spent Nuclear Fuel.” In International High-Level Radioactive Waste Management. Charlotte, NC. https://www.osti.gov/servlets/purl/1431544.

Recktenwald, G. D., and M. R. Deinert. 2012. “Cost Probability Analysis of Reprocessing Spent Nuclear Fuel in the US.” Energy Economics 34(6):1873-1881. https://doi.org/10.1016/j.eneco.2012.07.016.

Redmond, E., and N. Ashkeboussi. 2022. “Establishing a High Assay Low Enriched Uranium Infrastructure for Advanced Reactors.” Washington, DC: Nuclear Energy Institute. https://www.nei.org/CorporateSite/media/filefolder/resources/reports-and-briefs/NEI-White-Paper-Establishing-a-High-Assay-Low-Enriched-Uranium-Infrastructure-for-Advanced-Reactors-Jan-2022.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Regalbuto, M. 2021. “Independent Report: GAIN/EPRI/NEI April 2020 Virtual HALEU Workshop.” Presentation to the National Academies’ Committee on the Merits and Viability of Different Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors, September 28, 2021. https://www.nationalacademies.org/event/09-28-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-10-september-28-29-2021-public-sessions.

Regan, C., J. Hammelman, and J. Cuadrado. 2020. “Overview of the NRC’s Regulatory Programs on the Advanced Reactor Fuel Cycle.” Presented at the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 22.

Reset Steering Committee. 2018. Reset of America’s Nuclear Waste Management: Strategy and Policy. Stanford University Center for International Security and Cooperation and George Washington University Elliott School of International Affairs. October 15. https://fsi-live.s3.us-west-1.amazonaws.com/s3fs-public/reset_report_2018_final.pdf. Accessed April 21, 2022.

Reyes, J. 2021. “NuScale Power—A Scalable Clean Energy Solution.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, January 11, 2021. https://www.nationalacademies.org/event/01-11-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-january-11-2021-and-january-13-2021-meeting.

Rieman, C. R. 2013. “West Valley Demonstration Project: Successes and Challenges.” In Proceedings of WM ’13 Symposium. Phoenix, AZ.

Riley, B. J., J. McFarlane, G. D. DelCul, J. D. Vienna, C. I. Contescu, L. M. Hay, A. V. Savino, and H. E. Adkins. 2018. “Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors.” NTRD-MSR-2018-000379, PNNL-27723. Nuclear Technology Research and Development. Pacific Northwest National Laboratory and Oak Ridge National Laboratory, August 15. https://info.ornl.gov/Sites/Publications/Files/Pub114284.pdf.

Riley, B., J. McFarlane, G. Del Cul, J. Vienna, C. Contescu, and C. Forsberg. 2019. “Molten Salt Reactor Waste and Effluent Management Strategies: A Review.” Nuclear Engineering and Design 345(April 15):94-109. https://doi.org/10.1016/j.nucengdes.2019.02.002.

Rivers, J., J. Wheeler, and G. Couture. 2021. “Developing A Security Program for the X-Energy HALEU Fuel Fabrication Facility to Support Advanced Reactors.” Institute of Nuclear Materials Management 62nd Annual Meeting. https://resources.inmm.org/sites/default/files/2021-09/a1622.pdf.

Robel, M., J. Choi, B. B. Ebbinghaus, B. W. Sleaford, C. G. Bathke, B. A. Collins, Z. Beauvais, K. R. Hase, A. W. Prichard, and J. A. Blink. 2013. “A Safeguards and Security Assessment Comparing the Nuclear Material Attractiveness of Unirradiated and Irradiated Fuels Associated with Existing Power Reactors and Potential Future Small Modular Reactors.” https://www.osti.gov/servlets/purl/1088489.

Rodrigues, D., G. Durán-Klie, and S. Delpech. 2015. “Pyrochemical Reprocessing of Molten Salt Fast Reactor Fuel: Focus on the Reductive Extraction Step.” Nukleonika 60(4):907-914. https://doi.org/doi:10.1515/nuka-2015-0153.

Rodríguez-Penalonga, L., and B. Y. Moratilla Soria. 2017. “A Review of the Nuclear Fuel Cycle Strategies and the Spent Nuclear Fuel Management Technologies.” Energies 10(8). https://doi.org/10.3390/en10081235.

Rothwell, G., Wood, T., Daly, D. and Weimar, M. 2014. “Sustainability of Light Water Reactor Fuel Cycles.” Nuclear Energy and Sustainable Development: Selected Topics 74(December):S16-S23. https://doi.org/10.1016/j.enpol.2014.07.018.

Sackett, J., and E. D. Arthur. 2021. “The ARC-100 Advanced SMR.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, February 22. https://www.nationalacademies.org/event/02-22-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-february-22-and-23-2021-meeting.

Scheinman, L. 1987. The International Atomic Energy Agency and World Nuclear Order. New York: Routledge.

Schneider, E. A., M. R. Deinert, and K. B. Cady. 2009. “Cost Analysis of the US Spent Nuclear Fuel Reprocessing Facility.” Energy Economics 31(5):627-634. https://doi.org/10.1016/j.eneco.2008.12.011.

SCK-CEN. 2018. “BR2 Belgian Reactor 2 US National Scientific User Affiliate Facility User’s Guide.” Belgium: SCK-CEN. January.

Scott, L. M., M. P. Dion, K. K. Hogue, S. E. O’Brien, and G. T. Westphal. 2021. “Infrastructure and Testing Needs for Molten Salt Reactor Safeguards.” ORNL/TM-2021/1940. Oak Ridge, TN: Oak Ridge National Laboratory. March 1. https://doi.org/10.2172/1782030.

Selectra. 2021. “Electricity Tariffs in France: Compare Electricity Prices in 2021.” Paris, France: Selectra. https://en.selectra.info/energy-france/guides/electricity/tariffs.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Serco. 2011. “Literature Review of Partitioning and Transmutation.” Prepared for Nuclear Decommissioning Authority (NDA) Radioactive Waste Management Directorate (RWMD). United Kingdom: Serco. February. https://webarchive.nationalarchives.gov.uk/ukgwa/20211004151120/https://rwm.nda.gov.uk/publication/literature-review-of-partitioning-and-transmutation.

Shafer, J. 2021. “Advanced Research Project Agency-Energy (ARPA-E) Efforts Supporting Advanced Nuclear.” Presented at the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, September 13. https://www.nationalacademies.org/event/09-13-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-9-september-13-15-2021.

Sherman, S. R., and C. J. Knight. 2005. “Treatment Method for Fermi Barrel Sodium Metal Residues.” INL/EXT-05-00421. Idaho Falls, ID: Idaho National Laboratory. June 1. https://doi.org/10.2172/912436.

Shoesmith, D. W. 2000. “Fuel Corrosion Processes Under Waste Disposal Conditions.” Journal of Nuclear Materials 282(1, November 1):1-31. https://doi.org/10.1016/S0022-3115(00)00392-5.

Shoman, N., and M. Higgins. 2021. “Considerations for NMA of Molten Salt Reactors,” American Nuclear Society Winter Meeting, Washington, DC. November.

Shropshire, D., G. Black, and K. Araujo. 2021. “Global Market Analysis of Microreactors.” DOE Microreactor Program. Idaho Falls, ID: Idaho National Laboratory. https://gain.inl.gov/MicroreactorProgramTechnicalReports/Document-INL-EXT-21-63214.pdf.

Sivagami, K., K. Padmanabhan, A. C. Joy, and I. M. Nambi. 2019. “Microwave (MW) Remediation of Hydrocarbon Contaminated Soil Using Spent Graphite—An Approach for Waste as a Resource.” Journal of Environmental Management 230(January 15):151-158. https://doi.org/10.1016/j.jenvman.2018.08.071.

SNETP (Sustainable Nuclear Energy Technology Platform). 2011. “Thorium Cycles and Thorium as a Nuclear Fuel Component.” Strategic Research Agenda—Annex. Brussels, Belgium: Sustainable Nuclear Energy Technology Platform. January. Thorium Cycles and Thorium as a Nuclear Fuel Component.

Soares, A., A. Lintereur, B. R. Betzler, A. Johnsen, J. Flygare, L. G. Worrall, and W. Walters. 2020. “Nuclear Data Uncertainty Challenges in Molten Salt Reactor Safeguards.” In Oak Ridge, TN. https://www.osti.gov/biblio/1763462.

Sorensen, K. 2021. “Liquid-Fluoride Thorium Reactor Design and Fuel Cycle.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, January 13.

SRS (Savannah River Site). 2020. “Defense Waste Processing Facility.” December. https://www.srs.gov/general/news/factsheets/srr_dwpf.pdf.

Stamp, E. 2020. “This Sleek Building Is Actually a Nuclear Reactor.” Architectural Digest, March 23. https://www.architecturaldigest.com/story/sleek-building-actually-nuclear-reactor.

Stern, W. 2021. “IAEA Safeguards Considerations Associated with HALEU.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, May 17. https://www.nationalacademies.org/event/05-17-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-may-17-19-2021-meeting.

Subsidy Tracker. 2021. “NuScale Power.” https://subsidytracker.goodjobsfirst.org/prog.php?parent=nuscale-power&order=sub_year&sort=asc. Accessed December 30, 2021.

Suk, P., O. Chvála, G. I. Maldonado, and J. Frýbort. 2021. “Simulation of a NuScale Core Design with the CASL VERA Code.” Nuclear Engineering and Design 371(January):110956. https://doi.org/10.1016/j.nucengdes.2020.110956.

Swift, P. 2021. “Impacts of Nuclear Fuel Cycle Choices on Permanent Disposal of High-Activity Radioactive Waste.” Presented at the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, June 2. https://www.nationalacademies.org/event/06-01-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-6-part-1-june-1-2-2021.

Swift, P. N., and D. Sassani. 2019. “Impacts of Nuclear Fuel Cycle Choices on Permanent Disposal of High-Activity Radioactive Wastes.” SAND2019-5941C, 675860. https://www.osti.gov/biblio/1640197.

Szieberth, M., M. Halász, T. Reiss, and S. Fehér. 2013. “Fuel Cycle Studies on Minor Actinide Burning in Gas Cooled Fast Reactors.” In Proceedings of an International Conference Held in Paris, France, Track 8-Deployment and Scenarios. Paris, France: International Atomic Energy Agency. https://www-pub.iaea.org/MTCD/Publications/PDF/SupplementaryMaterials/P1665CD/Track8_Deployment_and_Scenarios.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Szondy, D. 2018. “Cost-Effective Method of Extracting Uranium from Seawater Promises Limitless Nuclear Power.” New Atlas, June 14, 2018. https://newatlas.com/nuclear-uranium-seawater-fibers/55033.

Tan, Y-Z., Z-Y. Xie, F. Peng, F-H. Qian, and H. J. Ming. 2021. “Optimal Mixing Scheme for Graphite–Bentonite Mixtures Used as Buffer Materials in High-Level Waste Repositories.” Environmental Earth Sciences 80(17):549. https://doi.org/10.1007/s12665-021-09809-x.

Taylor, R. (Ed.). 2015. Reprocessing and Recycling of Spent Nuclear Fuel. Woodhead Publishing Series in Energy. Oxford, UK: Woodhead Publishing. https://doi.org/10.1016/C2013-0-16483-5.

TerraPower. 2021a. The NatriumTM Program. May 18. https://www.terrapower.com/natrium-program-summary. Accessed April 21, 2022.

TerraPower. 2021b. “Additional TerraPower Information for Review Committees.” August.

TerraPower. 2022. “Additional Information Provided in Response to Fact Checking.” June 2.

Terrestrial Energy. 2021. “Response to the National Academy of Sciences Questionnaire on IMSR® Technology and Development.” February.

The Economist. 2022. “The First Underground Warren for Disposing of Spent Nuclear Fuel,” June 23, 2022. https://www.economist.com/science-and-technology/2022/06/22/the-first-underground-warren-for-disposing-of-spent-nuclear-fuel.

Todd, T. 2020. “Ceramic and TRISO Fuel Recycle Option.” Presented to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, December 8. https://www.nationalacademies.org/event/12-07-2020/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-december-7-8-2020-meeting.

Todd, T. 2021. “Trends in Nuclear Fuel Cycle Workforce.” Presented at the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, December 6.

Toki, M., and M. Pomper. 2013. “Time to Stop Reprocessing in Japan.” Arms Control Today 43(1, January/February):22-29.

Totemeier, A. 2021. “Lightbridge FuelTM Overview.” Presented at the Spring 2021 Nuclear Waste Technical Review Board Meeting, online, May 12. https://www.nwtrb.gov/docs/default-source/meetings/2021/may/totemeier.pdf?sfvrsn=4.

Touran, N. 2020. “Myths and Misconceptions About Thorium Nuclear Fuel.” What Is Nuclear, Updated September 8. https://whatisnuclear.com/thorium-myths.html.

Tracy, C. L. M. K. Dustin and R. C. Ewing. 2016. Policy: Reassess New Mexico’s nuclear-waste repository. Nature 529(January 13):149-151. https://doi.org/10.1038/529149a.

Triplett, B. S., E. P. Loewen, and B. J. Dooies. 2012. “PRISM: A Competitive Small Modular Sodium-Cooled Reactor.” Nuclear Technology 178(May):186-200.

Tuček, K., J. Carlsson, D. Vidović, and H. Wider. 2008. “Comparative Study of Minor Actinide Transmutation in Sodium and Lead-Cooled Fast Reactor Cores.” Progress in Nuclear Energy 50(2):382-388. March 1. https://doi.org/10.1016/j.pnucene.2007.11.021.

Tylka, M. M., J. L. Willit, J. Prakash, and M. A. Williamson. 2015. “Application of Voltammetry for Quantitative Analysis of Actinides in Molten Salts.” Journal of the Electrochemical Society 162(12):H852-H859. https://doi.org/10.1149/2.0281512jes.

Uhlíř, J., and M. Marecek. 2009. “Fluoride Volatility Method for Reprocessing of LWR and FR Fuels.” Journal of Fluorine Chemistry 130(1):89-93. https://doi.org/10.1016/j.jfluchem.2008.07.002.

UN (United Nations) Office of Disarmament Affairs. n.d.-a. “Treaty on the Non-Proliferation of Nuclear Weapons (NPT).” United Nations. https://www.un.org/disarmament/wmd/nuclear/npt. Accessed April 21, 2022.

UN Office of Disarmament Affairs. n.d.-b. Disarmament Treaties Database. https://treaties.unoda.org. Accessed April 21, 2022.

U.S. NRC (U.S. Nuclear Regulatory Commission). 1978. Federal Register, Notices, 43(101). May 24, 1978. https://www.govinfo.gov/content/pkg/FR-1978-05-24/pdf/FR-1978-05-24.pdf.

U.S. NRC. 1983. “Standard Format and Content for a Licensee Physical Security Plan for the Protection of Special Nuclear Material of Moderate or Low Strategic Significance.” NRC Regulatory Guide 5.59. Washington, DC: U.S. Nuclear Regulatory Commission, February 1983. https://www.nrc.gov/docs/ML1003/ML100341301.pdf.

U.S. NRC. 2000. “NRC Review of the Tokai-Mura Criticality Accident.” Washington, DC: U.S. Nuclear Regulatory Commission. https://www.nrc.gov/reading-rm/doc-collections/commission/secys/2000/secy2000-0085/attachment1.pdf.

U.S. NRC. 2005. “Regulatory Issue Summary 2005-22: Requirements for the Physical Protection During Transportation of Special Nuclear Material of Moderate and Low Strategic Significance.” 10 CFR Part 73 vs. Regulatory Guide 5.59 (1983). October 28. ML052000423. https://www.nrc.gov/reading-rm/doc-collections/gen-comm/reg-issues/2005/ri200522.pdf.

U.S. NRC. 2007. Licenses, certifications and approvals for nuclear power plants; Final rule. Federal Register 72(166):49437.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

U.S. NRC. 2009. “Material Categorization and Future Fuel Cycle Facility Security-Related Rulemaking.” SECY-09-0123. Washington, DC: U.S. Nuclear Regulatory Commission, September 4, 2009. https://www.nrc.gov/docs/ML1228/ML12285A057.pdf.

U.S. NRC. 2010. Waste Confidence Decision Update: Final Rule [10 CFR Part 51, 7590-01-P, NRC-2008-0482]. December 9. Rockville, MD: U.S. Nuclear Regulatory Commission. https://www.nrc.gov/docs/ML1033/ML103350186.pdf. Accessed March 14, 2022.

U.S. NRC. 2011. “Draft Regulatory Basis for Licensing and Regulating Reprocessing Facilities.” SECY-11-0163. Washington, DC: U.S. Nuclear Regulatory Commission, November 2011. https://www.nrc.gov/docs/ML1120/ML112081702.pdf.

U.S. NRC. 2013a. “Implementation Guidance for 10CFR37, Physical Protection of Category I and Category 2 Quantities of Radioactive Materials.” NUREG-2155. Washington, DC: U.S. Nuclear Regulatory Commission, February 2013. https://www.nrc.gov/docs/ML1305/ML13053A061.pdf.

U.S. NRC. 2013b. “Reprocessing Regulatory Framework—Status and Next Steps.” SECY-13-0093. Washington, DC: U.S. Nuclear Regulatory Commission, August 30, 2013. https://www.nrc.gov/reading-rm/doc-collections/commission/secys/2013/2013-0093scy.pdf.

U.S. NRC. 2014a. “Continued Storage of Spent Nuclear Fuel: Final Rule [NRC-2012-0246, RIN 3150-AJ20].” Federal Register 79(182):56238-56263. September 19. https://www.govinfo.gov/content/pkg/FR-2014-09-19/pdf/2014-22215.pdf.

U.S. NRC. 2014b. “Generic Environmental Impact Statement for the Continued Storage of Spent Nuclear Fuel, Final Report.” NUREG-2157. Washington, DC: U.S. Nuclear Regulatory Commission, September 2014. https://www.nrc.gov/docs/ML1419/ML14196A105.pdf.

U.S. NRC. 2014c. “Physical Security Best Practices for the Protection of Risk-Significant Radioactive Material.” NUREG-2166. Washington, DC: U.S. Nuclear Regulatory Commission, May 2014. https://www.nrc.gov/docs/ML1415/ML14150A382.pdf.

U.S. NRC. 2014d. “Safety and Regulatory Issues of the Thorium Fuel Cycle.” NUREG/CR-7176, ORNL/TM-2013/543. Washington, DC: U.S. Nuclear Regulatory Commission, 2014. https://www.nrc.gov/docs/ML1405/ML14050A083.pdf.

U.S. NRC. 2015. “Rulemaking for Enhanced Security of Special Nuclear Material, Regulatory Basis Document.” RIN number: 3150-AJ41; NRC Docket ID: NRC-2014-0118. Regulatory Basis Document. Washington, DC: U.S. Nuclear Regulatory Commission, January 2015. https://www.nrc.gov/docs/ML1432/ML14321A007.pdf.

U.S. NRC. 2016. Report to Congress Under Public Law 113-235: Effectiveness of Part 37 of Title 10 of the Code of Federal Regulations. https://www.nrc.gov/docs/ML1634/ML16347A398.pdf. Accessed April 21, 2022.

U.S. NRC. 2017. “Stages of the Nuclear Fuel Cycle.” Nuclear Materials, August 22, 2017. https://www.nrc.gov/materials/fuel-cycle-fac/stages-fuel-cycle.html.

U.S. NRC. 2018a. “Backgrounder on High Burnup Spent Nuclear Fuel.” U.S. NRC, October 1, 2018. https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/bg-high-burnup-spent-fuel.html.

U.S. NRC. 2018b. “Options and Recommendation for Physical Security for Advanced Reactors.” SRM-SECY-18-0076. Washington, DC: U.S. Nuclear Regulatory Commission, November 19, 2018. https://www.nrc.gov/docs/ML1832/ML18324A478.pdf.

U.S. NRC. 2019a. “Discontinuation of Rulemaking—Enhanced Security of Special Nuclear Material.” SECY-19-0095. Policy Issue (Notation Vote). Washington, DC: U.S. Nuclear Regulatory Commission, October 1, 2019. https://www.nrc.gov/docs/ML1915/ML19157A084.pdf.

U.S. NRC. 2019b. “Summary of Views of Some Technical Staff on the Alternate Approach to Conduct a Rulemaking Consistent with the 2015 Final Regulatory Basis.” SECY-19-0095: Enclosure 2. Washington, DC: U.S. Nuclear Regulatory Commission, October 17, 2019. https://www.nrc.gov/docs/ML1924/ML19248C233.pdf.

U.S. NRC. 2020a. “Accident Tolerant Fuel Regulatory Activities: Increased Enrichment.” U.S. NRC. November 13, 2020. https://www.nrc.gov/reactors/atf/enrichment.html.

U.S. NRC. 2020b. “Power Reactors.” Nuclear Reactors, April 29, 2020. https://www.nrc.gov/reactors/power.html.

U.S. NRC. 2020c. “Fuel Fabrication.” Nuclear Materials, December 2, 2020. https://www.nrc.gov/materials/fuel-cycle-fac/fuel-fab.html#cat1

U.S. NRC. 2020d. “Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material.” NUREG-2216. Washington, DC: U.S. Nuclear Regulatory Commission, August 2020. https://www.nrc.gov/docs/ML2023/ML20234A651.pdf.

U.S. NRC. 2020e. “Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities—Final Report.” NUREG-2215. Washington, DC: U.S. Nuclear Regulatory Commission, April 2020. https://www.nrc.gov/docs/ML2012/ML20121A190.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

U.S. NRC. 2020f. “Certification of Packages for Transportation of Unirradiated Material—Increased Enrichment.” U.S. NRC, September 18, 2020. https://www.nrc.gov/reactors/atf/cert-package-transport-unirradiated.html#increased.

U.S. NRC. 2020g. “Mixed Oxide Fuel Fabrication Facility Licensing.” U.S. NRC, December 2, 2020. https://www.nrc.gov/materials/fuel-cycle-fac/mox/licensing.html.

U.S. NRC. 2020h. “Path Forward and Recommendations for Certain Low-Level Radioactive Waste Disposal Rulemakings.” SECY-20-0098. Washington, DC: U.S. Nuclear Regulatory Commission. https://www.nrc.gov/docs/ML2014/ML20143A165.pdf.

U.S. NRC. 2020i. “NDAA Section 3116 Waste Incidental to Reprocessing (WIR) at the Idaho National Laboratory (INL) in Idaho—Idaho Nuclear Technical and Engineering Center (INTEC) Tank Farm Facility (TFF).” U.S. Nuclear Regulatory Commission, August 26, 2020. https://www.nrc.gov/waste/incidental-waste/wir-process/wir-locations/idaho-national-lab.html.

U.S. NRC. 2020j. “Consolidated Interim Storage Facility (CISF).” U.S. NRC. December 8, 2020. https://www.nrc.gov/waste/spent-fuel-storage/cis.html.

U.S. NRC. 2020k. “Locations of Low-Level Waste Disposal Facilities.” Nuclear Regulatory Commission: Radioactive Waste, March 12, 2020. https://www.nrc.gov/waste/llw-disposal/licensing/locations.html.

U.S. NRC. 2020l. “Safeguard Categories of SNM.” U.S. NRC. March 11, 2020. https://www.nrc.gov/security/domestic/mca/snm.html.

U.S. NRC. 2020m. “Backgrounder on Decommissioning Nuclear Power Plants.” U.S. NRC. July 8, 2020. https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/decommissioning.html.

U.S. NRC. 2021a. “Discontinuation of Rulemaking—Spent Fuel Reprocessing.” SECY-21-0026. Policy Issue (Notation Vote). Washington, DC: U.S. Nuclear Regulatory Commission, March 5, 2021. https://www.nrc.gov/docs/ML2030/ML20301A388.pdf.

U.S. NRC. 2021b. “Spent Fuel Reprocessing.” Federal Register, Notices, 86(143). July 29, 2021. https://www.govinfo.gov/content/pkg/FR-2021-07-29/pdf/2021-16173.pdf.

U.S. NRC. 2021c. “Defense in Depth.” U.S. NRC. March 9, 2021. https://www.nrc.gov/reading-rm/basic-ref/glossary/defense-in-depth.html.

U.S. NRC. 2021d. “Locations of Power Reactor Sites Undergoing Decommissioning.” U.S. Nuclear Regulatory Commission, November 10, 2021. https://www.nrc.gov/info-finder/decommissioning/power-reactor/index.html.

U.S. NRC. 2021e. “Fermi—Unit 1.” U.S. Nuclear Regulatory Commission, March 9, 2021. https://www.nrc.gov/info-finder/decommissioning/power-reactor/enrico-fermi-atomic-power-plant-unit-1.html.

U.S. NRC. 2021f. “West Valley Demonstration Project.” U.S. Nuclear Regulatory Commission, March 24, 2021. www.nrc.gov/info-finder/decommissioning/complex/wv.html.

U.S. NRC. 2021g. “Staff Requirements—SECY-19-0095—Discontinuation of Rulemaking—Enhanced Security of Special Nuclear Material,” August 4, 2021. https://www.nrc.gov/docs/ML2121/ML21217A065.pdf.

U.S. NRC. 2021h. “Fuel Cycle—Physical Security Requirements for Facilities with Category II Quantities of Special Nuclear Material Information Sheet.” U.S. Nuclear Regulatory Commission, October 8, 2021. https://www.nrc.gov/reactors/new-reactors/advanced/rulemaking-and-guidance/fuel-cycle.html.

U.S. NRC. 2022a. Fuel Qualification for Advanced Reactors—Final. NUREG-2246. Washington, DC: U.S. Nuclear Regulatory Commission. https://www.nrc.gov/docs/ML2206/ML22063A131.pdf.

U.S. NRC. 2022b. “Integral Molten Salt Reactor (IMSR).” U.S. Nuclear Regulatory Commission. May 31, 2022. https://www.nrc.gov/reactors/new-reactors/advanced/licensing-activities/pre-application-activities/imsr.html.

U.S. NRC. 2022c. “Backgrounder on Decommissioning Nuclear Power Plants.” U.S. Nuclear Regulatory Commission. June 23, 2022. https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/decommissioning.html.

U.S. NRC. 2022d. “Oklo Inc.—Denial of the Aurora Combined Operating License Application for Failure to Supply Information (EPID L-2020-NEW-0004 and EPID L-2020-NEW-0005).” Washington, DC: U.S. Nuclear Regulatory Commission. https://www.nrc.gov/docs/ML2135/ML21357A034.pdf.

U.S. NRC. n.d. “Nuclear Power Reactor Testing Needs and Prototype Plants for Advanced Reactor Designs.” https://www.nrc.gov/docs/ML1702/ML17025A353.pdf. Accessed February 23, 2022.

U.S. Nuclear Waste Technical Review Board. 2017. “Vitrified High-Level Radioactive Waste.” Revision 1, November 2017. https://www.nwtrb.gov/docs/default-source/facts-sheets/vitrified_hlw.pdf?sfvrsn=16.

Vaden, D. 2007. “Fuel Conditioning Facility Electrorefiner Model Predictions Versus Measurements.” INL/CON-07-12980, Pre-print. Idaho Falls, ID: Idaho National Laboratory. October. https://inldigitallibrary.inl.gov/sites/sti/sti/3984768.pdf.

van den Akker, B. P., and J. Ahn. 2013. “Performance Assessment for Geological Disposal of Graphite Waste Containing TRISO Particles.” Nuclear Technology 181(3):408-426. March 1. https://doi.org/10.13182/NT11-103.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Van der Stricht, S., and A. Janssens. 2010. Radioactive Effluents from Nuclear Power Stations and Nuclear Fuel Reprocessing Sites in the European Union, 2004-08. Radiation Protection 164. Luxembourg: European Commission. https://data.europa.eu/doi/10.2833/27366.

Van Rooyen, I. J., Subhashish M., and J. Rosales. 2018. “Effect of Neutron Irradiation Damage on Fission Product Transport in the SiC Layer of TRISO Fuel Particles.” In Proceedings of HTR 2018. Warsaw, Poland. https://www.osti.gov/servlets/purl/1478815.

Vandegrift, G. F., M. C. Regalbuto, S. Aase, A. Bakel, T. J. Battisti, D. Bowers, J. P. Byrnes, M. A. Clark, D. G. Cummings, J. W. Emery, J. R. Falkenberg, A. V. Gelis, C. Pereira, L. Hafenrichter, Y. Tsai, K. J. Quigley, and M. H. Vander Pol. 2004 “Designing and Demonstration of the UREX+ Process Using Spent Nuclear Fuel.” In ATALANTE 2004, 8. Nimes, France. https://inis.iaea.org/collection/NCLCollectionStore/_Public/36/008/36008582.pdf?r=1. Accessed April 21, 2022.

Vexler, A. 2021. “HALEU.” Presentation to the National Academies’ Committee on the Merits and Viability of Different Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors, online, September 15. https://www.nationalacademies.org/event/09-13-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-9-september-13-15-2021.

Vine, G. 2011. “Abridged History of Reactor and Fuel Cycle Technologies Development: A White Paper for the Reactor and Fuel Cycle Technology Subcommittee of the Blue Ribbon Commission.” Longenecker & Associates. https://cybercemetery.unt.edu/archive/brc/20120621004807/http://brc.gov/sites/default/files/documents/vine_abridged_history_of_reactor_and_fuel_cycle_technologies_development_final.pdf.

Von Baeckmann, A. 1988. “IAEA Safeguards in Nuclear-Weapon States.” IAEA Bulletin 1. https://www.iaea.org/sites/default/files/publications/magazines/bulletin/bull30-1/30103552224.pdf.

von Hippel, F. 2007. “Managing Spent Fuel in the United States: The Illogic of Reprocessing.” International Panel on Fissile Material. https://www.nrc.gov/docs/ML0817/ML081780779.pdf. Accessed April 21, 2022.

von Lensa, W., D. Vulpius, H.-J. Steinmetz, N. Girke, D. Bosbach, B. Thomauske, A.W. Banford, et al. 2011. “Treatment and Disposal of Irradiated Graphite and Other Carbonaceous Waste.” ATW—Internationale Zeitschrift Fur Kernenergie 56(4-5):263-269.

von Lensa, W., G. Brinkmann, J. Lillington, and F. Shahrokhi. 2020. The status quo on HTGR decommissioning. Nuclear Engineering and Design 359: 110456. April 1. https://doi.org/10.1016/j.nucengdes.2019.110456.

Wade, D. C., and R. N. Hill. 1997. “The Design Rationale of the IFR.” Progress in Nuclear Energy 31(1):13-42. January 1. https://doi.org/10.1016/0149-1970(96)00002-9.

Wallenius, J. 2021. “Fuel Cycle of SEALER-55.” Presented at the Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, February 23. https://www.nationalacademies.org/event/02-22-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-february-22-and-23-2021-meeting.

Wang, J., and S. Zhuang. 2019. “Extraction and Adsorption of U(VI) from Aqueous Solution Using Affinity Ligand-Based Technologies: An Overview.” Reviews in Environmental Science and Bio/Technology 18(3):437-452. https://doi.org/10.1007/s11157-019-09507-y.

Westfall, C. 2004. “Vision and Reality: The EBR-II Story.” Nuclear News (February):25-32. https://www.ne.anl.gov/About/reactors/EBR2-NN-2004-2-2.pdf. Accessed April 21, 2022.

Westinghouse Electric Company. 2003. “AP1000 Design Control Document, Rev. 3.” APP-GW-GL-700. Westinghouse Electric Company.

Westphal, B. R., G. L. Fredrickson, G. G. Galbreth, D. Vaden, M. D. Elliott, J. C. Price, E. M. Honeyfield, M. N. Patterson, and L. A. Wurth. 2013. “Pyroprocessing of Fast Flux Test Facility Nuclear Fuel.” In INL/CON-13-28161. Salt Lake City, UT. https://www.osti.gov/biblio/1111514.

White House. 1993. “Nonproliferation and Export Control Policy Statement.” Fact sheet. September 27, 1993. Washington, DC: Executive Office of the President.

Wickham, A., H.-J. Steinmetz, P. O’Sullivan, and M. I. Ojovan. 2017. “Updating Irradiated Graphite Disposal: Project ‘GRAPA’ and the International Decommissioning Network.” Journal of Environmental Radioactivity 171:34-40. May 1. https://doi.org/10.1016/j.jenvrad.2017.01.022.

Wigeland, R., T. Taiwo, M. Todosow, W. Halsey, and J. Gehin. 2009. “AFCI Options Study.” INL/EXT-10-17639. Idaho Falls, ID: Idaho National Laboratory. September 1. https://doi.org/10.2172/978356. Accessed April 21, 2022.

Wigeland, R., T. Taiwo, H. Ludewig, M. Todosow, W. Halsey, J. Gehin, R. Jubin, et al. 2014. “Nuclear Fuel Cycle Evaluation and Screening—Final Report.” Fuel Cycle Research & Development. U.S. Department of Energy, October 8, 2014. https://fuelcycleevaluation.inl.gov/Shared%20Documents/ES%20Main%20Report.pdf.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

Williamson, M. A. 2020. “Metallic Fuel Recycling.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, December 8. https://www.nationalacademies.org/event/12-07-2020/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-december-7-8-2020-meeting.

Williamson, M., and T. Taiwo. 2021. Responses to the Committee’s Additional Information Requests. September 13.

Willrich, M., and R. K. Lester. 1977. Radioactive Waste Management and Regulation. New York: Free Press.

WNA (World Nuclear Association). 2017a. “Mixed Oxide (MOX) Fuel.” Updated October 2017. https://world-nuclear.org/information-library/nuclear-fuel-cycle/fuel-recycling/mixed-oxide-fuel-mox.aspx. Accessed April 21, 2022.

WNA. 2017b. “Lithium.” World Nuclear Association. October 2017. https://world-nuclear.org/information-library/current-and-future-generation/lithium.aspx.

WNA. 2020a. “Uranium Enrichment.” September. https://world-nuclear.org/information-library/nuclear-fuel-cycle/conversion-enrichment-and-fabrication/uranium-enrichment.aspx.

WNA. 2020b. “Generation IV Nuclear Reactors.” December. https://www.world-nuclear.org/information-library/nuclear-fuel-cycle/nuclear-power-reactors/generation-iv-nuclear-reactors.aspx.

WNA. 2020c. “Thorium.” November. http://www.world-nuclear.org/information-library/current-and-future-generation/thorium.aspx.

WNA. 2021a. “Uranium Mining Overview.” September. https://world-nuclear.org/information-library/nuclear-fuel-cycle/mining-of-uranium/uranium-mining-overview.aspx.

WNA. 2021b. “U.S. Nuclear Fuel Cycle.” May. https://world-nuclear.org/information-library/country-profiles/countries-t-z/usa-nuclear-fuel-cycle.aspx.

WNA. 2021c. “Nuclear Fuel and Its Fabrication.” October. https://world-nuclear.org/information-library/nuclear-fuel-cycle/conversion-enrichment-and-fabrication/fuel-fabrication.aspx.

WNA. 2021d. “Fast Neutron Reactors.” Updated August. https://world-nuclear.org/information-library/current-and-future-generation/fast-neutron-reactors.aspx.

WNA. 2021d. “Russia’s Nuclear Fuel Cycle.” Country Profile. Updated May. https://world-nuclear.org/information-library/country-profiles/countries-o-s/russia-nuclear-fuel-cycle.aspx.

WNA. 2021e. “Nuclear Power in the United Kingdom.” Country Profile. Updated August. https://www.world-nuclear.org/information-library/country-profiles/countries-t-z/united-kingdom.aspx.

WNA. 2021f. “Nuclear Power in Japan.” Country Profile. Updated June. https://world-nuclear.org/information-library/country-profiles/countries-g-n/japan-nuclear-power.aspx.

WNA. 2021g. “Nuclear Power in India.” Country Profile. Updated June. https://world-nuclear.org/information-library/country-profiles/countries-g-n/india.aspx.

WNA. 2021h. “China’s Nuclear Fuel Cycle.” Country Profile. Updated March. https://world-nuclear.org/information-library/country-profiles/countries-a-f/china-nuclear-fuel-cycle.aspx.

WNA. 2021i. “Research Reactors.” Updated June. https://world-nuclear.org/information-library/non-power-nuclear-applications/radioisotopes-research/research-reactors.aspx.

WNA. 2022a. “World Nuclear Association.” https://world-nuclear.org. Accessed April 21, 2022.

WNA. 2022b. “Conversion and Deconversion.” Updated January. https://world-nuclear.org/information-library/nuclear-fuel-cycle/conversion-enrichment-and-fabrication/conversion-and-deconversion.aspx.

WNA. 2022c. “Nuclear Power in France.” Updated January. https://www.world-nuclear.org/information-library/country-profiles/countries-a-f/france.aspx.

WNA. 2022d. “Physics of Uranium and Nuclear Energy.” February. https://world-nuclear.org/information-library/nuclear-fuel-cycle/introduction/physics-of-nuclear-energy.aspx.

WNISR (World Nuclear Industry Status Report). 2022. “World Nuclear Industry Status Report.” https://www.worldnuclearreport.org.

WNN (World Nuclear News). 2010. “PBMR Facing Massive Cuts.” February 18. https://www.world-nuclear-news.org/C_PBMR_facing_massive_cuts_1802101.html.

WNN. 2018. “Reprocessing Ceases at UK’s Thorp Plant.” World Nuclear News, November 14, 2018. https://www.world-nuclear-news.org/Articles/Reprocessing-ceases-at-UKs-Thorp-plant.

WNN. 2020a. “Congress Approves Nuclear Energy Funding for FY2021.” World Nuclear News, December 23, 2020. https://world-nuclear-news.org/Articles/Congress-approves-nuclear-energy-funding-for-FY202.

WNN. 2020b. “Rosatom and US DOC Welcome Change to Uranium Agreement.” World Nuclear News, October 8, 2020. https://world-nuclear-news.org/Articles/Rosatom-and-US-DOC-welcome-change-to-uranium-agree.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×

WNN. 2021a. “Joint Venture Formed to Spur SMR Deployment in Sweden.” February 15, 2021. https://world-nuclear-news.org/Articles/Joint-venture-formed-to-spur-SMR-deployment-in-Swe

WNN. 2021b. “Chinese Fast Reactor Begins High-Power Operation.” February 19, 2021. https://world-nuclear-news.org/Articles/Chinese-fast-reactor-begins-high-power-operation.

WNN. 2021c. “Preliminary Design of TRISO-X Fuel Plant Completed.” World Nuclear News, November 2, 2021. https://www.world-nuclear-news.org/Articles/Preliminary-design-of-TRISO-X-fuel-plant-completed.

WNN. 2021d. “US Conversion Plant Gears Up for Next 40 Years.” World Nuclear News, April 14, 2021. https://world-nuclear-news.org/Articles/US-conversion-plant-gears-up-for-next-40-years.

WNN. 2022a. “One-Year Delay in Canadian Repository Site Selection.” World Nuclear News. August 15, 2022. https://www.world-nuclear-news.org/Articles/One-year-delay-in-Canadian-repository-site-selecti.

WNN. 2022b. “Chinese Molten-Salt Reactor Cleared for Start Up.” World Nuclear News. August 9, 2022. https://www.world-nuclear-news.org/Articles/Chinese-molten-salt-reactor-cleared-for-start-up.

Wood, E. S., J. T. White, B. Jaques, D. Burkes, and P. Demkowicz. 2020. “10 - Advances in Fuel Fabrication.” In Advances in Nuclear Fuel Chemistry, edited by M. H. A. Piro, pp. 371-418. Woodhead Publishing Series in Energy. Woodhead Publishing. https://doi.org/10.1016/B978-0-08-102571-0.00011-2.

Worrall, A. 2013. “Utilization of Used Nuclear Fuel in a Potential Future US Fuel Cycle Scenario.” In WM2013 Conference. Phoenix, AZ. https://www.ourenergypolicy.org/wp-content/uploads/2013/09/Pub40177.pdf.

Worrall, A. 2021. “Rationale for Reprocessing and Recycling.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, June 2, 2021. https://www.nationalacademies.org/event/06-01-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-6-part-1-june-1-2-2021.

Worth, R. N., A. Theodosiou, W. Bodel, J. D. Arregui-Mena, A. J. Wickham, A. N. Jones, and P. M. Mummery. 2021. “The Distribution and Selective Decontamination of Carbon-14 from Nuclear Graphite.” Journal of Nuclear Materials 556:153167. December 1. https://doi.org/10.1016/j.jnucmat.2021.153167.

X-energy. 2022. “X-Energy’s TRISO-X Selects Oak Ridge Horizon Center for First Commercial Advanced Reactor Fuel Fabrication Facility in North America.” X-energy, April 4. https://x-energy.com/media/news-releases/x-energy-triso-x-selects-oak-ridge-horizon-center-for-first-commercial-advanced-reactor-fuel-fabrication-facility-in-north-america.

Xu, X., L. Xu, J. Ao, Y. Liang, C. Li, Y. Wang, C. Huang, et al. 2020a. “Ultrahigh and Economical Uranium Extraction from Seawater via Interconnected Open-Pore Architecture Poly(Amidoxime) Fiber.” Journal of Materials Chemistry A 8(42):22032-22044. https://doi.org/10.1039/D0TA07180C.

Xu, S. G., S. Chester, K. Choi, and E. Bulemela. 2020b. “Characteristic Waste Streams from Small Modular Reactors Considered for Deployment in Canada.” CNL Nuclear Review 9(1):83-92. https://pubs.cnl.ca/doi/full/10.1139/CNR.2019.00008.

Yang, W.S. 2012 “Fast Reactor Physics and Computational Methods.” Nuclear Engineering and Technology 44(2):177-198. https://doi.org/10.5516/NET.01.2012.504.

Yardley, B. W. D., R. C Ewing, and R. A. Whittleston. 2016. “Deep-Mined Geological Disposal of Radioactive Waste.” Elements: An International Magazine of Mineralogy, Geochemistry, and Petrology 12(4). August.

Zaetta, A., F. Varaine, Ch. Chabert, E. Dupont, J. F. Lebrat, and J. Tommasi. 2005. “La Faisabilité Scientifique de La Transmutation Des Déchets à Vie Longue.” Commissariat à l’énergie atomique et aux énergies alternatives. https://inis.iaea.org/collection/NCLCollectionStore/_Public/38/041/38041742.pdf.

Zhan, L., Y. Bo, T. Lin, and Z. Fan. 2021. “Development and Outlook of Advanced Nuclear Energy Technology.” Energy Strategy Reviews 34:100630. March 1. https://doi.org/10.1016/j.esr.2021.100630.

Zhang, H. 2021. “On China’s Nuclear Fuel Cycle.” Presentation to the National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, December 6. https://www.nationalacademies.org/event/12-06-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advanced-nuclear-reactors-meeting-12-december-6-7-2021.

Zhang, J., L. Li, S. He, and Y. Chen. 2016. “Calculation of Radioactivity and Dose Rate of Activated Corrosion Products in Water-Cooled Fusion Reactor.” Science and Technology of Nuclear Installations 2016:6051834. https://doi.org/10.1155/2016/6051834.

Zhu, L., W. Duan, J. Xu, and Y. Zhu. 2012. “Uranium Extraction from TRISO-Coated Fuel Particles Using Supercritical CO2 Containing Tri-n-Butyl Phosphate.” Journal of Hazardous Materials 241-242:456-462. https://doi.org/10.1016/j.jhazmat.2012.09.072.

Zuidema, P. 2021. “Radioactive Waste Management Issues to Be Considered When Evaluating Different Nuclear Fuel Cycle and Reactor Variants.” National Academies’ Committee on Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Reactors, June 7. https://www.nationalacademies.org/event/06-07-2021/merits-and-viability-of-different-nuclear-fuel-cycles-and-technology-options-and-the-waste-aspects-of-advancednuclear-reactors-meeting-6-part-2-june-7-2021.

Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 217
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 218
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 219
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 220
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 221
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 222
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 223
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 224
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 225
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 226
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 227
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 228
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 229
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 230
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 231
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 232
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 233
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 234
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 235
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 236
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 237
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 238
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 239
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 240
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 241
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 242
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 243
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 244
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 245
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 246
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 247
Suggested Citation:"References." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press. doi: 10.17226/26500.
×
Page 248
Next: Appendix A: Biographical Sketches of the Committee and Project Staff »
Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors Get This Book
×
 Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors
Buy Paperback | $46.00 Buy Ebook | $36.99
MyNAP members save 10% online.
Login or Register to save!
Download Free PDF

The United States has deployed commercial nuclear power since the 1950s, and as of 2021, nuclear power accounts for approximately 20 percent of U.S. electricity generation. The current commercial nuclear fleet consists entirely of thermal-spectrum, light water reactors operating with low-enriched uranium dioxide fuel in a once-through fuel cycle. In recent years, the U.S. Congress, U.S. Department of Energy, and private sector have expressed considerable interest in developing and deploying advanced nuclear reactors to augment, and possibly replace, the U.S. operating fleet of reactors, nearly all of which will reach the end of their currently licensed operating lives by 2050. Much of this interest stems from the potential ability of advanced reactors and their associated fuel cycles - as claimed by their designers and developers - to provide a number of advantages, such as improvements in economic competitiveness, reductions in environmental impact via better natural resource utilization and/or lower waste generation, and enhancements in nuclear safety and proliferation resistance.

At the request of Congress, this report explores merits and viability of different nuclear fuel cycles, including fuel cycles that may use reprocessing, for both existing and advanced reactor technologies; and waste management (including transportation, storage, and disposal options) for advanced reactors, and in particular, the potential impact of advanced reactors and their fuel cycles on waste generation and disposal.

READ FREE ONLINE

  1. ×

    Welcome to OpenBook!

    You're looking at OpenBook, NAP.edu's online reading room since 1999. Based on feedback from you, our users, we've made some improvements that make it easier than ever to read thousands of publications on our website.

    Do you want to take a quick tour of the OpenBook's features?

    No Thanks Take a Tour »
  2. ×

    Show this book's table of contents, where you can jump to any chapter by name.

    « Back Next »
  3. ×

    ...or use these buttons to go back to the previous chapter or skip to the next one.

    « Back Next »
  4. ×

    Jump up to the previous page or down to the next one. Also, you can type in a page number and press Enter to go directly to that page in the book.

    « Back Next »
  5. ×

    Switch between the Original Pages, where you can read the report as it appeared in print, and Text Pages for the web version, where you can highlight and search the text.

    « Back Next »
  6. ×

    To search the entire text of this book, type in your search term here and press Enter.

    « Back Next »
  7. ×

    Share a link to this book page on your preferred social network or via email.

    « Back Next »
  8. ×

    View our suggested citation for this chapter.

    « Back Next »
  9. ×

    Ready to take your reading offline? Click here to buy this book in print or download it as a free PDF, if available.

    « Back Next »
Stay Connected!