Thermohydraulic Performance in SMR Reactors with Mixed Oxide (U, Th)O2 Fuel: A Computational Approach
DOI:
https://doi.org/10.15392/2319-0612.2024.2674Keywords:
CFD, SMR, MOXAbstract
This paper presents a computational study on the thermohydraulic performance of subchannels within Small Modular Reactor (SMR) configurations using Mixed Oxide (MOX) fuels comprising (U, Th)O2 alongside subchannels containing conventional UO2. The research aims to evaluate these fuel types operational efficiency and safety within the context of small-scale reactors. Utilizing a Computational Fluid Dynamics (CFD) model implemented in OpenFOAM, this study considers the variability of the thermophysical properties of the materials as influenced by temperature changes. The findings reveal that MOX fuels exhibit lower maximum temperatures than UO2, suggesting a more uniform radial temperature distribution. Moreover, both the cladding and coolant temperatures remain within safe operational limits across all scenarios examined, highlighting the potential of MOX fuels to enhance the safety and efficiency of SMRs. This analysis advances our understanding of the thermal behavior of advanced fuel compositions in nuclear reactors. It underscores the importance of comprehensive thermohydraulic studies in the design and operation of next-generation nuclear power systems.
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[1] INGERSOLL, D., T. Deliberately small reactors and the second nuclear era. Progress in Nuclear Energy, v. 51, n. 4-5, p. 589-603, 2009.
[2] CHEN, B.; YU, N.; FU, L.; ZHU, Y.; VAN REE, T.; WU, Y. Mixed oxides in nuclear fuels. In: Elsevier (Ed). Metal Oxides in Energy Technologies. Cambridge, MA, US: Elsevier Inc., 2019. p. 73–89. ISBN 978-0-12-811167-3.
[3] IAEA. Potential of thorium based fuel cycles to constrain plutonium and reduce long lived waste toxicity. IAEA-TECDOC-1349, International Atomic Energy Agency, Vienna, 2003.
[4] CARELLI, M. D.; INGERSOLL, D. T. Handbook of Small Modular Nuclear Reactors, Cambridge, MA, US: Elsevier Inc., 2015. p. 1–516. ISBN 978-0-85709-853-5.
[5] STEFANI, G. L.; MAIORINO, J. R.; MOREIRA, J. M. L.; SANTOS, T. A.; ROSSI, P. C. R. Feasibility to convert an advanced PWR from UO2 to a mixed (U,Th)O2 core. PROCEEDINGS OF THE INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE 2017, Belo Horizonte, Brazil. Anais...International Nuclear Atlantic Conference, 2017.
[6] BETANCOURT, M. C.; GARCÍA HERNÁNDEZ, C. R.; DOMINGUEZ, D. S.; ROJAS MAZAIRA, L. Y.; BRAYNER, C. A.; ROSALES GARCÍA, J. A.; IGLESIAS, S. M. Mixed-oxide fuel strategies in an integral pressurized water reactor. Progress in Nuclear Energy, v. 139, 103844, 2021.
[7] ERIGHIN, M. A. A 48-month extended fuel cycle for the B&W mPowerTM small modular nuclear reactor. International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics. v.2, p. 1315-1330, 2012.
[8] WANG, M.; WANG, Y.; TIAN, W.; QIU, S.; SU, G. H. Recent progress of CFD applications in PWR thermal hydraulics study and future directions. Annals of Nuclear Energy. v.150, 107836, 2021.
[9] JASAK, H. OpenFOAM: Open source CFD in research and industry. International Journal of Naval Architecture and Ocean Engineering. v. 1, n. 2, p. 89–94, 2009.
[10] JASAK, H.; JEMCOV, A.; TUKOVIC, Z. OpenFOAM : A C ++ Library for Complex Physics Simulations. International Workshop on Coupled Methods in Numerical Dynamics. p. 1–20, 2007.
[11] OpenFOAM. OpenFOAM: Programmers Guide v1812. Available at: https://foam.sourceforge.net/docs/Guides-a4/ProgrammersGuide.pdf. Accessed on: 17 Apr. 2023.
[12] GULLBERG, R. Computational fluid dynamics in OpenFOAM. Mesh Generation and Quality. TKP, v. 4555, 2017.
[13] FABRITIUS, B., TABOR, G. Improving the quality of finite volume meshes through genetic optimisation. Engineering with Computers, v.32, 425–440, 2016.
[14] IAEA. Thermophysical Properties of Materials for Nuclear Engineering: A Tutorial and Collection of Data. IAEA-THPH, International Atomic Energy Agency, Vienna, 2008.
[15] IAEA. Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors. IAEA-TECDOC-1496, International Atomic Energy Agency, Vienna, 2006.
[16] MOUKALLED, F.; MANGANI L.; DARWISH M. The finite volume method in computational fluid dynamics. Fluid Mechanics and Its Applications. v. 113, 2016.
[17] HACHE, G.; CHUNG, H. M. The History of LOCA Embrittlement Criteria. PROCEEDINGS OF THE TWENTY-EIGHTH WATER REACTOR SAFETY INFORMATION MEETING 2001, Bethesda, MD, United States. Anais… 28th Water Reactor Safety Information Meeting, 2001.
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