Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling

References

• S. M. FEINBERG, “Discussion Comment,” in Record of Proceedings Session B-10, Proc. Int. Conf. Peaceful Uses of Atomic Energy, Vol. 9, No. 2, p. 447, Geneva, Switzerland, 1958, United Nations.
   Google Scholar
• R. PETROSKI, B. FORGET, and C. FORSBERG, “Neutronic Evaluation of Breed-and-Burn Reactor Fuel Types Using an Infinite-Medium Depletion Approximation,” Proc. Physor 2010, Pittsburgh, Pennsylvania, May 9–14, 2010, American Nuclear Society (2010).
   Google Scholar
• F. HEIDET and E. GREENSPAN, “Neutron Balance Analysis for Sustainability of Breed and Burn Reactors,” Nucl. Sci. Eng., 171, 1, 13 (2012); https://doi.org/https://doi.org/10.13182/NSE10-114.
   Web of Science ®Google Scholar
• H. SEKIMOTO and K. RYU, “A New Reactor Burnup Concept CANDLE,” Proc. Physor 2000, Pittsburgh, Pennsylvania, 2000, American Nuclear Society (2000).
   Google Scholar
• J. GILLELAND et al., “Novel Reactor Designs to Burn Non-Fissile Fuel,” Proc. 2008 Int. Congress Advances in Nuclear Power Plants (ICAPP 2008), Anaheim, California, June 8–12, 2008, American Nuclear Society (2008).
   Google Scholar
• T. OBARA, K. KUWAGAKI, and J. NISHIYAMA, “Feasibility of Burning Wave Fast Reactor Concept with Rotational Fuel Shuffling,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)Yekaterinburg, Russian Federation, June 26–29, 2017, IAEA-CN245-051International Atomic Energy Agency, (2017).
   Google Scholar
• K. KUWAGAKI, J. NISHIYAMA, and T. OBARA, “Concept of Stationary Wave Reactor with Rotational Fuel Shuffling,” Nucl. Sci. Eng., 191, 2, 178 (2018); https://doi.org/https://doi.org/10.1080/00295639.2018.1463744.
   Web of Science ®Google Scholar
• E. GREENSPAN, “Maximum Fuel Utilization in Fast Reactors Without Chemical Reprocessing,” Project No. 09-769,U.S. Department of Energy, Nuclear Energy University Programs (2012); https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202009/NEUP_Project_No_09-769_Final_Report.pdf (current as of Dec. 7, 2020).
   Google Scholar
• E. GREENSPAN, “Advanced Burner Reactor with Breed-and-Burn Thorium Blankets for Improved Economics and Resource Utilization,” Project No. 12-3486, U.S. Department of Energy, Nuclear Energy University Programs (2015); https://neup.inl.gov/SiteAssets/Final%20%20Reports/FY%202012/12-3486%20NEUP%20Final%20Report.pdf#search=Project%20No%2E%2012%2D3486 (current as of Dec. 7, 2020).
   Google Scholar
• A. E. DUBBERLEY et al., “SuperPRISM Oxide and Metal Fuel Core Designs,” Proc. ICONE 8, Baltimore, Maryland, April 2–6, 2000.
   Google Scholar
• T. K. KIM et al., “Core Design Studies for a 1000 MWth Advanced Burner Reactor,” Ann. Nucl. Energy, 36, 3, 331 (2009); https://doi.org/https://doi.org/10.1016/j.anucene.2008.12.021.
   Web of Science ®Google Scholar
• E. A. HOFFMAN, W. S. YANG, and R. N. HILL, “Preliminary Core Design Studies for the Advanced Burner Reactor over a Wide Range of Conversion Ratios,” ANL-AFCI-177, Argonne National Laboratory (2008).
   Google Scholar
• “Comparative Assessment of Thermophysical and Thermohydraulic Characteristics of Lead, Lead-Bismuth and Sodium Coolants for Fast Reactors,” International Atomic Energy Agency (2002).
   Google Scholar
• S. QVIST, J. HOU, and E. GREENSPAN, “Design and Performance of 2D and 3D-Shuffled Breed-and-Burn Cores,” Ann. Nucl. Energy, 85, 93 (2015); https://doi.org/https://doi.org/10.1016/j.anucene.2015.04.007.
   Web of Science ®Google Scholar
• G. L. HOFMAN, L. C. WALTERS, and T. H. BAUER, “Metallic Fast Reactor Fuels,” Prog. Nucl. Energy, 31, 1–2, 83 (1997); https://doi.org/https://doi.org/10.1016/0149-1970(96)00005-4.
   Google Scholar
• J. LEPPÄNEN, “Serpent–A Continuous-Energy Monte Carlo Reactor Physics Burnup Calculation Code,” VTT Technical Research Centre of Finland (2015).
   Google Scholar
• M. B. CHADWICK et al., “ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology,” Nucl. Data Sheets, 107, 12, 2931 (2006); https://doi.org/https://doi.org/10.1016/j.nds.2006.11.001.
   Google Scholar
• “Multiphysics Modeling, Finite Element Analysis, and Engineering Simulation Software,” COMSOL 5.4a; https://www.comsol.com (current as of Apr. 5, 2020).
   Google Scholar
• V. K. HOANG, J. NISHIYAMA, and T. OBARA, “Design Concepts of Small CANDLE Reactor with Melt-Refining Process,” Prog. Nucl. Energy, 108, 233 (2018); https://doi.org/https://doi.org/10.1016/j.pnucene.2018.05.019.
   Web of Science ®Google Scholar
• V. K. HOANG, J. NISHIYAMA, and T. OBARA, “Effects of Compensating for Fuel Losses During the Melt-Refining Process for a Small CANDLE Reactor,” Ann. Nucl. Energy, 135, 106969 (2020); https://doi.org/https://doi.org/10.1016/j.anucene.2019.106969.
   Web of Science ®Google Scholar
• J. A. KARIM, J. NISHIYAMA, and T. OBARA, “Application of Melt and Refining Procedures in the CANDLE Reactor Concept,” Ann. Nucl. Energy, 90, 275 (2016); https://doi.org/https://doi.org/10.1016/j.anucene.2015.12.001.
   Web of Science ®Google Scholar
• P. DENG et al., “Coupled Neutron and Gamma Heating Calculation Based on VARIANT Transport Solutions,” Nucl. Sci. Eng., 193, 12, 1310 (2019); https://doi.org/https://doi.org/10.1080/00295639.2019.1621617.
   Web of Science ®Google Scholar
• D. C. CRAWFORD, D. L. PORTER, and S. L. HAYES, “Fuels for Sodium-Cooled Fast Reactors: US Perspective,” J. Nucl. Mater., 371, 202 (2007); https://doi.org/https://doi.org/10.1016/j.jnucmat.2007.05.010.
   Web of Science ®Google Scholar
• S. QVIST and E. GREENSPAN, “Design Space Analysis for Breed-and-Burn Reactor Cores,” Nucl. Sci. Eng., 182, 197 (2016); https://doi.org/https://doi.org/10.13182/NSE14-135.
   Web of Science ®Google Scholar
• C. D. SANZO and E. GREENSPAN, “A Search for Minimum Volume of Breed and Burn Cores,” Proc. ICAPP ’12, Chicago, Illinois, June 24–28, 2012, American Nuclear Society (2012).
   Google Scholar
• V. PRAKASH et al., “Experimental Qualification of Subassembly Design for Prototype Fast Breeder Reactor,” Nucl. Eng. Des., 241, 8, 3325 (2011); https://doi.org/https://doi.org/10.1016/j.nucengdes.2011.04.040.
   Web of Science ®Google Scholar
• S. D. PARK et al., “Thermal-Hydraulic Analysis of a 7-Pin Sodium Fast Reactor Fuel Bundle with a New Pattern of Helical Wire Wrap Spacer,” Ann. Nucl. Energy, 114, 198 (2018); https://doi.org/https://doi.org/10.1016/j.anucene.2017.12.027.
   Web of Science ®Google Scholar