Design and Neutronic, Thermal-Hydraulic Analysis of DSCF Assembly for a SMR and Investigation of the Effect on the Thermal Power Uprate

References

• “Advances in Small Modular Reactor Technology Developments,” International Atomic Energy Agency (2018).
   Google Scholar
• D. T. INGERSOLL, “Deliberately Small Reactors and the Second Nuclear Era,” Prog. Nucl. Energy, 51, 4–5, 589 (2009); https://doi.org/10.1016/j.pnucene.2009.01.003.
   Web of Science ®Google Scholar
• G. LOCATELLI and B. MIGNACCA, “Small Modular Nuclear Reactors,” in Future Energy, pp. 151–169, Elsevier (2020); https://doi.org/10.1016/B978-0-08-102886-5.00008-6.
   Google Scholar
• Advances in Small Modular Reactor Technology Developments, International Atomic Energy Agency (2014).
   Google Scholar
• L. LI et al., “MELCOR Severe Accident Analysis for a Natural Circulation Small Modular Reactor,” Prog. Nucl. Energy, 100, 197 (2017); https://doi.org/10.1016/j.pnucene.2017.06.003.
   Web of Science ®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
• J. N. REYES JR., “NuScale Plant Safety in Response to Extreme Events,” Nucl. Technol., 178, 2, 153 (2012); https://doi.org/10.13182/NT12-A13556.
   Web of Science ®Google Scholar
• P. HEJZLAR, M. J. DRISCOLL, and M. S. KAZIMI, “Thermal Hydraulics—I. 4. High-Performance Annular Fuel for Pressurized Water Reactors,” Trans. Am. Nucl. Soc., 84, 192 (2001).
   Google Scholar
• P. HEJZLAR and M. S. KAZIMI, “Annular Fuel for High-Power-Density Pressurized Water Reactors: Motivation and Overview,” Nucl. Technol., 160, 1, 2 (2007); https://doi.org/10.13182/NT160-2-15.
   Web of Science ®Google Scholar
• M. ZAIDABADI, G. R. ANSARIFAR, and M. H. ESTEKI, “Thermal Hydraulic Analysis of VVER-1000 Nuclear Reactor with Dual-Cooled Annular Fuel Using K–ω SST Turbulence Model,” Ann. Nucl. Energy, 101, 118 (2017); https://doi.org/10.1016/j.anucene.2016.09.027.
   Web of Science ®Google Scholar
• H. Z. RISHEHRI and M. Z. NEJAD, “Conceptual Design of an Innovative I&XC Fuel Assembly for a SMR Based on Neutronic/Thermal-Hydraulic Calculations at the BOC,” Kerntechnik, 87, 1, 91 (2022); https://doi.org/10.1515/kern-2021-1012.
   Web of Science ®Google Scholar
• G. R. ANSARIFAR, M. H. ESTEKI, and M. ZAIDABADI, “Investigation of the Dual-Cooled Annular Fuel Effect on the Thermal Power Uprate in a VVER-1000 Nuclear Reactor,” Nucl. Technol., 195, 1, 105 (2016); https://doi.org/10.13182/NT15-90.
   Web of Science ®Google Scholar
• C. H. SHIN et al., “Thermal Hydraulic Performance Assessment of Dual-Cooled Annular Nuclear Fuel for OPR-1000,” Nucl. Eng. Des., 243, 291 (2012); https://doi.org/10.1016/j.nucengdes.2011.12.010.
   Web of Science ®Google Scholar
• J. V. DONNELLY, “WIMS-CRNL: A User’s Manual for the Chalk River Version of WIMS,” AECL–8955, Atomic Energy of Canada Ltd (1986).
   Google Scholar
• T. B. FOWLER and D. R. VONDY, “Nuclear Reactor Core Analysis Code: CITATION,” ORNL-TM-2496, Oak Ridge National Laboratory (1969).
   Google Scholar
• “GAMBIT 2.2 Tutorial Guide,” Fluent, Incorporated (2004).
   Google Scholar
• ANSYS FLUENT Theory Guide 15.0, p. 33, ANSYS (2013).
   Google Scholar
• NuSCALE POWER LLC, “NuScale Standard Plant Design Certification Application,” U.S. Nuclear Regulatory Commission (2020).
   Google Scholar
• A. SADEGH-NOEDOOST et al., “Investigations of the Fresh-Core Cycle-Length and the Average Fuel Depletion Analysis of the NuScale Core,” Ann. Nucl. Energy, 136, 106995 (2020); https://doi.org/10.1016/j.anucene.2019.106995.
   Web of Science ®Google Scholar
• H. ZHU et al., “Theoretical and Experimental Study on Single-Phase Natural Circulation Under Inclined Conditions,” J. Nucl. Sci. Technol., 50, 3, 304 (2013); https://doi.org/10.1080/00223131.2013.772444.
   Web of Science ®Google Scholar
• M. ZAIDABADI NEJAD and G. ANSARIFAR, “Design of a Small Modular Nuclear Reactor with Dual Cooled Annular Fuel and Investigation of the Fuel Inner Radius Effect on the Power Peaking Factor and Natural Circulation Parameters,” Ann. Nucl. Energy, 138, 107185 (2020a); https://doi.org/10.1016/j.anucene.2019.107185.
   Web of Science ®Google Scholar
• D. CARPENTER et al., “High Performance Fuel Design for Next Generation PWRs,” Technical Report, Massachusetts Institute of Technology (2006).
   Google Scholar
• Nuclear Reactor Design, Y. OKA, Ed., Springer Japan (2014).
   Google Scholar
• B. E. LAUNDER and D. B. SPALDING, Lectures in Mathematical Models of Turbulence, Academic Press (1972).
   Google Scholar
• M. ZAIDABADI NEJAD and G. ANSARIFAR, “Optimal Design of a Small Modular Reactor Core with Dual Cooled Annular Fuel Based on the Neutronic and Natural Circulation Parameters,” Nucl. Eng. Des., 360, 110518 (2020b); https://doi.org/10.1016/j.nucengdes.2020.110518.
   Web of Science ®Google Scholar
• Z. RAHNAMA and G. R. ANSARIFAR, “Nanofluid Application for Heat Transfer, Safety, and Natural Circulation Enhancement in the NuScale Nuclear Reactor as a Small Modular Reactor Using Computational Fluid Dynamic (CFD) Modeling via Neutronic and Thermal-Hydraulics Coupling,” Prog. Nucl. Energy, 138, 103796 (2021); https://doi.org/10.1016/j.pnucene.2021.103796.
   Web of Science ®Google Scholar
• M. M. EL-WAKIL, Nuclear Heat Transport, International TextBook Company (1971).
   Google Scholar