Simulation of the NuScale SMR and Investigation of the Effect of Load-Following on Component Lifetimes

References

• “Net Zero by 2050. A Roadmap for the Global Energy Sector,” International Energy Agency (2021); https://www.iea.org/reports/net-zero-by-2050.
   Google Scholar
• “Advanced Nuclear Technology: Advanced Light Water Reactors Utility Requirements Document Small Modular Reactors Inclusion Summary,” Electric Power Research Institute (2014).
   Google Scholar
• D. T. INGERSOLL et al., “Can Nuclear Power and Renewable Energies Be Friends?” 15555, Societe Francaise d’Energie Nucleaire, France (2015); http://inis.iaea.org/search/search.aspx?orig_q=RN:49010199.
   Google Scholar
• D. J. MCDOWELL et al., “A Technical and Economic Assessment of LWR Flexible Operation for Generation and Demand Balancing to Optimize Plant Revenue,” INL/EXT-21-65443-Rev001, Idaho National Laboratory (Dec. 2021); https://doi.org/10.2172/1844211.
   Google Scholar
• Non-baseload Operation in Nuclear Power Plants: Load Following and Frequency Control Modes of Flexible Operation, Nuclear Energy Series no. NP-T-3.23, International Atomic Energy Agency (2018); https://www.iaea.org/publications/11104/non-baseload-operation-in-nuclear-power-plants-load-following-and-frequency-control-modes-of-flexible-operation.
   Google Scholar
• P. MORILHAT et al., “Nuclear Power Plant Flexibility at EDF,” hal-01977209 (2019); https://hal-edf.archives-ouvertes.fr/hal-01977209/document.
   Google Scholar
• A. LOKHOV, “Load-Following with Nuclear Power Plants,” NEA News, 29.2, 18 (2011).
   Google Scholar
• Technical and Economic Aspects of Load Following with Nuclear Power Plants, Nuclear Energy Agency, Organisation for Economic Co-operation Development Publishing (2011).
   Google Scholar
• J. VUJIĆ et al., “Small Modular Reactors: Simpler, Safer, Cheaper?” Energy, 45, 1, 288 (Sep. 2012); https://doi.org/10.1016/j.energy.2012.01.078.
   Web of Science ®Google Scholar
• N. TODREAS, “1—Small Modular Reactors (SMRs) for Producing Nuclear Energy: An Introduction,” in Handbook of Small Modular Nuclear Reactors (2nd ed.), D. T. INGERSOLL and M. D. CARELLI, Eds., pp. 3–27, Woodhead Publishing (2021); https://doi.org/10.1016/B978-0-12-823916-2.00001-1.
   Google Scholar
• Technology Roadmap for Small Modular Reactor Deployment, Nuclear Energy Series no. NR-T-1.18, International Atomic Energy Agency (2021); https://www.iaea.org/publications/14861/technology-roadmap-for-small-modular-reactor-deployment.
   Google Scholar
• “Advances in Small Modular Reactor Technology Developments. A Supplement to: IAEA Advanced Reactors Information System (ARIS),” 2022 Ed., International Atomic Energy Agency (2022); http://inis.iaea.org/search/search.aspx?orig_q=RN:51111609.
   Google Scholar
• D. T. INGERSOLL et al., “NuScale Small Modular Reactor for Co-generation of Electricity and Water,” Desalination, 340, 84 (2014); https://doi.org/10.1016/j.desal.2014.02.023.
   Web of Science ®Google Scholar
• M. W. KENNARD and J. E. HARBOTTLE, “BWR Control Blade Replacement Strategies,” International Atomic Energy Agency, p. 1011 (2000).
   Google Scholar
• J. A. TURNER et al., “The Virtual Environment for Reactor Applications (VERA): Design and Architecture,” J. Comput. Phys., 326, 544 (Dec. 2016); https://doi.org/10.1016/j.jcp.2016.09.003.
   Web of Science ®Google Scholar
• P. SUK et al., “Simulation of a NuScale Core Design with the CASL VERA Code,” Nucl. Eng. Des., 371, 110956 (Jan. 2021); https://doi.org/10.1016/j.nucengdes.2020.110956.
   Web of Science ®Google Scholar
• T. LANGE et al., “Preliminary CRUD Analysis and Sensitivity Studies for NuScale SMR,” CASL-U-2018-1504-000, Consortium for Advanced Simulation of Light Water Reactors, Oak Ridge National Laboratory (Jan. 2018).
   Google Scholar
• “NuScale Standard Plant Design Certification Application,” NuScale LLC Report, NuScale Power, LLC (June 2020).
   Google Scholar
• J. N. REYES and P. LORENZINI, “NuScale Power: A New Approach to Commercial Nuclear Power,” New Nuclear Frontiers, Canadian Nuclear Society (June 2009).
   Google Scholar
• Z. LIU and J. FAN, “Technology Readiness Assessment of Small Modular Reactor (SMR) Designs,” Prog. Nucl. Energy, 70, 20 (Jan. 2014); https://doi.org/10.1016/j.pnucene.2013.07.005.
   Web of Science ®Google Scholar
• “NuScale Power Announces an Additional 25 Percent Increase in NuScale Power Module Output; Additional Power Plant Solutions,” Business Wire (Nov. 10, 2020); https://www.businesswire.com/news/home/20201110005452/en/NuScale-Power-Announces-an-Additional-25-Percent-Increase-in-NuScale-Power-Module%E2%84%A2-Output-Additional-Power-Plant-Solutions (current as of Jan. 18, 2022).
   Google Scholar
• B. HAUGH and A. MOHAMED, “Comparison of a NuScale SMR Conceptual Core Design Using CASMO5/SIMULATE5 and MCNP5,” presented at PHYSOR 2012: Advances in Reactor Physics—Linking Research, Industry, and Education, Knoxville, Tennessee, April 2012.
   Google Scholar
• B. KOCHUNAS et al., “VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion,” Nucl. Sci. Eng., 185, 1, 217 (Jan. 2017); https://doi.org/10.13182/NSE16-39.
   Web of Science ®Google Scholar
• S. PALMTAG et al., “VERA Common Input Manual,” CASL Report CASL-U-2014-0014-003, Consortium for Advanced Simulation of Light Water Reactors, Oak Ridge National Laboratory (July 2019).
   Google Scholar
• “VERAInView,” Consortium for Advanced Simulation of Light Water Reactors; https://github.com/CASL/VeraInView (current as of Jul. 17, 2018).
   Google Scholar
• B. COLLINS et al., “Stability and Accuracy of 3D Neutron Transport Simulations Using the 2D/1D Method in MPACT,” J. Comput. Phys., 326, 612 (Dec. 2016); https://doi.org/10.1016/j.jcp.2016.08.022.
   Web of Science ®Google Scholar
• R. SALKO et al., “CTF: A Modernized, Production-Level, Thermal Hydraulic Solver for the Solution of Industry-Relevant Challenge Problems in Pressurized Water Reactors,” Nucl. Eng. Des., 397, 111927 (Oct. 2022); https://doi.org/10.1016/j.nucengdes.2022.111927.
   Web of Science ®Google Scholar
• T. M. PANDYA et al., “Implementation, Capabilities, and Benchmarking of Shift, a Massively Parallel Monte Carlo Radiation Transport Code,” J. Comput. Phys., 308, 239 (Mar. 2016); https://doi.org/10.1016/j.jcp.2015.12.037.
   Web of Science ®Google Scholar
• B. HAUGH and R. FERRER, “CASMO5 PWR Methods and Validation Report,” Studsvik Scandpower Report SSP-14-P01012-R Rev, Vol. 1 (2015).
   Google Scholar
• J. RHODES, J. HYKES, and R. FERRER, “SIMULATE5—Advanced Three-Dimensional Multigroup Reactor Analysis Code,” SSP-10438 Rev. 3, Studsvik Scandpower (2012).
   Google Scholar
• B. T. REARDEN and M. A. JESSEE, “SCALE Code System,” Oak Ridge National Laboratory (2018).
   Google Scholar
• M. A. JESSEE et al., “Lattice Physics Calculations Using the Embedded Self-Shielding Method in Polaris, Part I: Methods and Implementation,” Ann. Nucl. Energy, 150, 107830 (Jan. 2021); https://doi.org/10.1016/j.anucene.2020.107830.
   Web of Science ®Google Scholar
• “NuScale Power, LLC—Submittal of Technical Report, ‘Pressure and Temperature Limits Methodology,’” TR-1015-18177, Rev. 2,” NuScale Power, LLC.
   Google Scholar