Closed nuclear fuel cycle strategy for NuScale-like reactor: safety parameters evaluation
DOI:
https://doi.org/10.15392/2319-0612.2024.2630Keywords:
SMR, NuScale, GANEX, UREX+, Closed Nuclear Fuel CycleAbstract
The present study evaluates the potential implementation of two different closed fuel cycle strategies for a NuScale-like reactor core. After undergoing three burnup cycles of approximately 12 MWd/kgU in the NuScale-like initial core and five years of cooling in a spent fuel pool, the spent fuel was theoretically reprocessed using GANEX or UREX+ methods. These reprocessed fuel compositions were then mixed with thorium (Th) and inserted into specific batch positions of the core. As a result, the proposed NuScale-like core configurations contain fuel assemblies loaded with both conventional uranium-based fuel and reprocessed fuel, resulting in the following combinations: UO2 and GANEX spiked with Th, and UO2 and UREX+ spiked with Th. The primary goal is to assess the safety margins of the proposed cores and compare them with the reference case. The results indicate that all scenarios with reprocessed fuel improved the fuel temperature reactivity coefficient and maximum initial excess of reactivity, while varying the boron concentration in the coolant. Additionally, it was found that both proposed cores met the power peak factor (PPF) design requirements, despite the high PPF value observed at the C03 central position. The simulations were performed using the Serpent code version 2.1.32, developed by VTT.
Downloads
References
[1] IAEA - International Atomic Energy Agency. Advances in Small Modular Reactor Technology Developments. Supplement to: IAEA Advanced Reactors Information System (ARIS) 2020 Edition, Vienna: IAEA, 2020.
[2] GOODMAN, D. Small Modular Reactors (SMRs): the case of developing countrie. In: Daniel, T. Handbook of Small Modular Nuclear Reactors. Sawston, UK: Woodhead Publishing, 2014. p. 595– 609. ISBN 978-0-12-823916-2. DOI: https://doi.org/10.1016/B978-0-12-823916-2.00023-0
[3] KANG, H. O.; LEE, B. J.; LIM, S. G. Light water SMR development status in Korea. Nuclear Engineering and Design, v. 419, p. 112966, 2024. DOI: https://doi.org/10.1016/j.nucengdes.2024.112966
[4] AL-SALHABI, A.; ALHABIB, A.; ALHARBI, T.; ALJOHANI, M.; SHAMS, A.; AL-ATHEL, K.; ALWAFI, A. The Feasibility of Small Modular Reactors (SMRs) in the Energy Mix of Saudi Arabia. Nuclear Engineering and Design, v. 418, p. 112896, 2024. DOI: https://doi.org/10.1016/j.nucengdes.2023.112896
[5] BUTT, H. N.; ILYAS, M.; AHMAD, M.; AYDOGAN, F. Assessment of passive safety system of a Small Modular Reactor (SMR). Annals of Nuclear Energy, v. 98, p. 191-199, 2016. DOI: https://doi.org/10.1016/j.anucene.2016.07.018
[6] DIAZ-PESCADOR, E.; YURII, B.; MATTHIAS, J.; SOEREN, K. NuScale-like SMR Model Development and Applied Safety Analyses with the Code Chain Serpent-DYN3D-ATHLET. Annals of Nuclear Energy, v. 418, p. 112909, 2024. DOI: https://doi.org/10.1016/j.nucengdes.2024.112909
[7] USNRC – Nuclear Regulatory Comission. NRC to Issue Rule Certifying NuScale Small Modular Reactor. Supplement to: Office of Public Affairs, Washington: USNRC, 2022.
[8] NUSCALE. New uk nnl study supports the ability of the nuscale power module to reduce plutonium stockpiles. Disponível em: https://www.nuscalepower.com/en/news/press-releases/2016/nuscale-announces-mox-capability. Acesso em: 17 jan. 2024.
[9] FRIDMAN, E.; YURII, B.; VALTAVIRTA, J.; SOEREN, K. Definition of the neutronics benchmark of the NuScale-like core. Nuclear Engineering and Technology, v. 55, n. 10, p. 3639-3647, 2023. DOI: https://doi.org/10.1016/j.net.2023.06.029
[10] WNA – World Nuclear Association. Processing of used nuclear fuel. Disponível em: https://world-nuclear.org/information-library/nuclear-fuel-cycle/fuel-recycling/processing-of-used-nuclear-fuel/. Acesso em: 22 jun. 2024.
[11] MIGUIRDITCHIAN, M; CHAREYRE, L.; HERES, X.; HILL, C. GANEX: Adaptation of the DIAMEX-SANEX process for the group actinide separation. Supplement to: Advanced Nuclear Fuel Cycles and Systems, Global, 2007.
[12] VANDEGRIFT, G. et al. Lab-scale demonstration of the urex+ process, 2004.
[13] LEPPÄNEN, J.; PUSA, M.; VIITANEN, T.; VALTAVIRTA, V.; KALTIAISENAHO, T. The Serpent Monte Carlo code: Status, development and applications in 2013. Annals of Nuclear Energy (Oxford), v. 142, p 142-150, 2023. DOI: https://doi.org/10.1016/j.anucene.2014.08.024
[14] HORELIK, N. Benchmark for Evaluation and Validation of Reactor Simulations (BEAVRS). Supplement to: Massachusetts Institute of Technology, 2013.
[15] WARIN, D. Future nuclear fuel cycles: Prospect and challenges for actinide recycling. Materials Science and Engineering, v. 9, p 012063, 2010. DOI: https://doi.org/10.1088/1757-899X/9/1/012063
[16] REGALBUTO, M.C. Alternative separation and extraction: Urex+ processes for actinide and targeted fission product recover. In: Nash, K.L., Lumetta, G.J. Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment, UK: Woodhead Publishing, 2011. p. 176–200. ISBN 978-0-12-823916-2. DOI: https://doi.org/10.1533/9780857092274.2.176
[17] IAEA - International Atomic Energy Agency. Role of Thorium to Supplement Fuel Cycles of Future Nuclear Energy Systems. Supplement to: Number NF-T-2.4 in Nuclear Energy Serie, Vienna: IAEA, 2012.
[18] AMATULLAH, A.; PERMANA, S.; IRWANTO, D.; AIMON, A. H. Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycle. Nuclear Engineering and Design, v. 418, p. 112934, 2024. DOI: https://doi.org/10.1016/j.nucengdes.2024.112934
[19] LEPPANEN, J. Serpent – a continuous-energy Monte Carlo reactor physics burnup calculation code. VTT Technical Research, Centre of Finland, 2019.
[20] CHADWICK, M.B. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data. Nuclear Data Sheets, v. 112, n. 12, p. 2887- 2996, 2011. DOI: https://doi.org/10.1016/j.nds.2011.11.002
[21] DEMAZIERE, C.; ESPINOZA, V. H. S.; ZENTNER, I. Advanced numerical simulation and modeling for reactor safety – contributions from the CORTEX, McSAFER, and METIS projects. EPJ Nuclear Science. Technology, v. 8, p. 12, 2011. DOI: https://doi.org/10.1051/epjn/2022026
[22] CARVALHO, K. A.; PAULA, G. P.; ARAÚJO, M. H. S.; SANTOS, A. A. C.; SILVA, V.; SANTIAGO, T. A. V.; CABRAL, R. G. Closing the nuclear fuel cycle: strategic approaches for NuScale-like reactor. Nuclear Engineering and Design, 2024. Submitted article. DOI: https://doi.org/10.1016/j.nucengdes.2024.113672
[23] LAMARSH, J. R.; BARATTA, A. J. Introduction to Nuclear Engineering. New York, NY, US: Pearson College, 2001. ISBN 978-0201824988.
[24] DUDERSTADT, J. J. Nuclear Reactor Analysis. New York, NY, US: Wiley, 1976. ISBN 978-0471223634.
[25] VIEIRA, T. A. S.; BARROS, G. P.; CAMPOLINA, D.; VASCONCELOS, V.; SANTOS, A. A. C.; Study of a fine-mesh 1:1 Computational Fluid Dynamics – Monte Carlo neutron transport coupling method with discretization uncertainty estimation. Annals of Nuclear Energy, v. 148, p. 107718, 2020. DOI: https://doi.org/10.1016/j.anucene.2020.107718
Downloads
Published
Issue
Section
Categories
License
Copyright (c) 2025 Keferson Almeida, Graiciany de Paula Barros, Matheus Henrique dos Santos Araújo, Rebeca Cabral Gonçalves, Tiago Augusto Santiago Vieira, Vitor Silva, Andre Augusto Campagnole dos Santos
This work is licensed under a Creative Commons Attribution 4.0 International License.
Licensing: The BJRS articles are licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons license, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons license and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/
How to Cite
