Analysis of Fuel Burnup and Transmutations at High Burnup of Sodium Fast Breeder Reactor

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Nehal Mohamed
https://orcid.org/0000-0002-5480-6996
Moustafa Aziz
M. El Ghazaly
Ibrahim Bashter

Abstract

In this paper, the Monte Carlo N-Particle extended  computer code (MCNP) were used to design a model of the European Sodium-cooled Fast Reactor. The multiplication factor, conversion factor, delayed neutrons fraction, doppler constant, control rod worth, sodium void worth, masses for major heavy nuclei, radial and axial power distribution at high burnup are studied. The results show that the reactor breeds fissile isotopes with a conversion ratio of 0.994 at fuel burnup 70 (GWd/T), and minor actinides are buildup inside the reactor core. The study aims to check the efficiency of the model on the calculation of the neutronic parameters of the core at high burnup.

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1.
Mohamed N, Aziz M, El Ghazaly M, Bashter I. Analysis of Fuel Burnup and Transmutations at High Burnup of Sodium Fast Breeder Reactor. Baghdad Sci.J [Internet]. 2022 Dec. 5 [cited 2023 Jan. 28];19(6(Suppl.):1551. Available from: https://bsj.uobaghdad.edu.iq/index.php/BSJ/article/view/7409
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References

Merk B, Litskevich D, Bankhead M, Taylor RJ. An innovative way of thinking nuclear waste management – Neutron physics of a reactor directly operating on SNF. PLOS ONE. 2017. Jul; 12(7): 1-19.

Hill RN, Therios I, Cipiti BB, Kim HD. Sodium-Cooled Fast Reactor Proliferation Resistance and Physical Protection White Paper. NNSA. 2020 Oct; 12214: 1-25. Available from: https://www.osti.gov/servlets/purl/1710232/

Tran TQ, Lee D. Neutronic simulation of the CEFR experiments with the nodal diffusion code system RAST-F. Nucl Eng Technol. 2022; 54(7): 2635–2649.

Saha U, Devan K, Bachchan A, Pandikumar G, Ganesan S. Neutron radiation damage studies in the structural materials of a 500 MWe fast breeder reactor using DPA cross-sections from ENDF / B-VII.1. Pramana – J Phys. 2018; 90(4): 46-61.

Maslov NV, Grishanin EI, Alekseev PN. The possibility of improving inherent safety BN-800 by the use of fuel assembly with (U, Pu)C microfuel. Izv vuzov Yad Energ. 2019 Mar; 2019(1): 71–84.

Rineiski A, Mériot C, Marchetti M, Krepel J, Coquelet-Pascal C, Tsige-Tamirat H, et al. ESFR-SMART Core Safety Measures and Their Preliminary Assessment. J Nucl Eng Radiat Sci. 2021; 8(1): 1130-1140.

Pelowitz DB. MCNPX User’s Manual Version 2.7.0. Los Alamos Sci. 2011.

Galfas AA, Fayyadh IK, Hassan HA, Aziz AK. Study of Reactivity Effect on Reactor Power by Using the Neutronic- Thermohydrolic Coupling. Baghdad Sci J. 2012 Sep; 9(3): 459–465.

Fridman E, Velarde FA, Otero PR, Tsige-Tamirat H, Antonio J, García-Herranz N, et al. Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results. J Nucl Eng Radiat Sci. 2021 Jul; 8(1).011301: 1056-1066. https://doi.org/10.1115/1.4048905

Abbood AS, Ibraheem IJ. Synthesis of Carbon Nano Rods from Plastic Waste (PP) Using MgO AS A Catalyst. Baghdad Sci J. 2020 Jun; 17(2): 609-613.

Fridman E, Velarde FA, Otero PR, Tsige-Tamirat H, Antonio J, García-Herranz N, et al. Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results. J Nucl Eng Radiat Sci. 2021 Jul; 8(1). 011302: 1067-1077. DOI: https://doi.org/10.1115/1.4048765

Davies U, Margulis M, Shwageraus E, Fridman E, García-Herranz N, Antonio J, et al. Evaluation of the ESFR end of cycle state and detailed analysis of spatial distributions of reactivity coefficients. EPJ Web Conf. 2021; 247: 02001. DOI:10.1051/epjconf/202124702001

Mohamed N, Aziz M, Bashter I. Studying the effect of assembly homogenization on fuel burn-up for a sodium-cooled fast breeder reactor. J Korean Phys Soc. 2021 Jul; 79(2): 160–167.

Antonio J, García-Herranz N, Krepel J, Margulis M, Baker U, Shwageraus E, et al. Decay Heat Characterization for the European Sodium Fast Reactor. J Nucl Eng Radiat Sci. 2022; 8(1): 1051-1060.

Stauff NE, Kim TK, Taiwo TA, Buiron L, Rimpault G, Lee YK, et al. Evaluation of the OECD/NEA/SFR-UAM Neutronics Reactivity Feedback and Uncertainty Benchmarks. IAEA. 2017; 49(44): 149-160.

Fensin ML, Hendricks JS, Anghaie S. The Enhancements and Testing for the MCNPX 2.6.0 Depletion Capability. Nucl Technol. 2010 Apr; 170(1): 68–79.

Nhan MN, Jo TY, Lee HS, Cherezov A, Lee DJ. Whole-core Monte Carlo Analysis of MOX-3600 Core in NEA-SFR Benchmark Using MCS Code. Proceedings of the KNS Fall Meeting . 2018.