Monitoring and simulation of the fuel irradiation behavior in nuclear reactors based on phononic crystal structure

• Published in: Scientific reports Vol. 13; no. 1; p. 12319
• Main Authors: Sayed, Fatma A., Elsayed, Hussein A., Eissa, M. F., Aly, Arafa H., Mehaney, Ahmed
• Format: Journal Article
• Language: English
• Published: London Nature Publishing Group UK 29.07.2023; Nature Publishing Group; Nature Portfolio
• Subjects: 639/301; 639/624; 639/705; 639/766; Crystal structure; Experimental research; Fabrication; Fuels; Humanities and Social Sciences; Irradiation; Mechanical properties; multidisciplinary; Nondestructive testing; Nuclear fuels; Nuclear reactors; Plutonium; Porosity; Radiation; Radioactive wastes; Reactors; Science; Science (multidisciplinary); Uranium; Uranium oxide
• ISSN: 2045-2322; 2045-2322
• DOI: 10.1038/s41598-023-39298-w

We have presented in the current work a novel idea for simulating the irradiation behaviors of the nuclear fuel pellets in nuclear reactors by using a one-dimensional defective phononic crystal (1D-DPnC) design was presented. The transmission spectra of the incident mechanical waves were considered basic data for expressing the characteristics of different nuclear fuel-pellets. Herein, the density, sound speed, and Young’s modulus of the fuel-pellets represent the key parameters that are influenced by the irradiation behaviors of these pallets. Mixed plutonium–uranium oxide (MOX) nuclear fuel is considered the main fuel in the present study. In addition, a comparison is performed for this fuel with other types of nuclear fuels. Moreover, the mechanical properties of these MOX-pellets are dependent on the porosity, the ratio of oxygen-to-metal (O/M), and the plutonium (Pu-content). The theoretical treatments depend on the transfers matrix method to compute the transmission spectra through the 1D-DPnC. The numerical findings provided that the MOX-pellet has the highest performance compared to other fuel pellets and with sensitivity equal to 59.388 × 10 3  Hz s/m. It was also reported that the effects of the percentage of the O/M and Pu- content in MOX had a minor effect in a comparison with the impact of porosity. The theoretical simulation agreed extremely with the experimental data reported for these nuclear fuels. Because of the close relationship between sound speed and density, this sensor can be utilized to monitor the porosity, O/M, Pu-content, and density of fuel-pellets as a quick and non-destructive evaluation technique in a nuclear fuel fabrication laboratory. This article has proven theoretically that MOX fuel produced from nuclear waste of uranium dioxide and plutonium dioxide gives excellent results compared to other types of nuclear fuels, and this agrees with experimental researches. Thus, it may contribute in preserving the environment from nuclear waste, and this can be considered a novel kind of purification of environmental pollution treatment.