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基于声子晶体结构的核反应堆燃料辐照行为监测与模拟

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

作者信息

Sayed Fatma A, Elsayed Hussein A, Eissa M F, Aly Arafa H, Mehaney Ahmed

机构信息

TH-PPM Group, Physics Department, Faculty of Sciences, Beni-Suef University, Beni Suef, 62514, Egypt.

出版信息

Sci Rep. 2023 Jul 29;13(1):12319. doi: 10.1038/s41598-023-39298-w.

Abstract

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 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.

摘要

在当前工作中,我们提出了一种通过使用一维缺陷声子晶体(1D-DPnC)设计来模拟核反应堆中核燃料芯块辐照行为的新想法。入射机械波的透射光谱被视为表达不同核燃料芯块特性的基础数据。在此,燃料芯块的密度、声速和杨氏模量代表了受这些芯块辐照行为影响的关键参数。混合钚 - 铀氧化物(MOX)核燃料被视为本研究中的主要燃料。此外,还对这种燃料与其他类型的核燃料进行了比较。而且,这些MOX芯块的力学性能取决于孔隙率、氧与金属的比例(O/M)以及钚含量(Pu含量)。理论处理依赖于转移矩阵法来计算通过1D-DPnC的透射光谱。数值结果表明,与其他燃料芯块相比,MOX芯块具有最高的性能,灵敏度等于59.388×10 Hz s/m。还报道了与孔隙率的影响相比,MOX中O/M百分比和Pu含量的影响较小。理论模拟与这些核燃料报道的实验数据高度吻合。由于声速和密度之间的密切关系,这种传感器可作为核燃料制造实验室中的一种快速无损评估技术,用于监测燃料芯块的孔隙率、O/M、Pu含量和密度。本文从理论上证明,由二氧化铀和二氧化钚的核废料产生的MOX燃料与其他类型的核燃料相比具有优异的结果,这与实验研究一致。因此,它可能有助于保护环境免受核废料污染,这可被视为一种新型的环境污染治理净化方式。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/8d77/10387093/519ba6e996c7/41598_2023_39298_Fig1_HTML.jpg

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