辐照U-10Mo杨氏模量的退化

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Chaoyue Jin , Zhexiao Xie , Luning Chen , Xingdi Chen , Jing Zhang , Shurong Ding , Xiaobin Jian
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引用次数: 0

摘要

对参考文献中四点弯曲实验结果的理论分析表明,重辐照U-10Mo燃料的有效杨氏模量显著降低。然而,潜在的机制需要充分阐明。本研究首先采用基于燃料骨架蠕变的体积生长应变模型和基于孔隙率的宏观蠕变速率模型,对含铀- 10mo燃料箔辐照诱导的单片燃料板热-力耦合行为进行了数值研究。几种燃料板弯曲试样的预测平均厚度与实验测量结果吻合较好,验证了所采用的模型、算法和得到的辐照U-10Mo燃料宏观孔隙度值。通过随后的四点弯曲试验直接模拟,确定了不同辐照水平下U-10Mo燃料的有效杨氏模量值,数值模拟得到的辐照U-10Mo试样宏观力学响应与实验数据吻合。在排除燃料孔隙度的影响后,发现致密铀- 10mo燃料骨架的杨氏模量随裂变密度或宏观孔隙度的增加而降低,从而成为辐照铀- 10mo燃料有效杨氏模量下降的主要原因。此外,建立了铀- 10mo燃料骨架在室温下的杨氏模量分别作为裂变密度和宏观孔隙度的函数的数学模型。预测结果表明,当考虑燃料骨架杨氏模量的退化时,von Mises应力将显著降低,等效蠕变应变可能有明显增加。该工作为基于u - 10mo的燃料元件或组件辐照诱导热力学行为的高精度建模奠定了基础。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
On the degradation of Young's modulus of irradiated U-10Mo
Theoretical analysis of the four-point bending experimental results from the reference has demonstrated that the effective Young's modulus of heavily-irradiated U-10Mo fuel undergoes a significant reduction. However, the underlying mechanisms need to be fully elucidated. In this study, the irradiation-induced thermo-mechanical coupling behaviors of monolithic fuel plates are first numerically investigated by employing the fuel skeleton creep-based volumetric growth strain model and the porosity-related macroscale creep rate model for the contained U-10Mo fuel foils. The predicted average thicknesses for the bending specimens from several fuel plates align well with the experimental measurements, validating the adopted models, algorithms and the obtained macroscale porosity values for irradiated U-10Mo fuel. The values of effective Young's modulus of U-10Mo fuel after different levels of irradiation are identified through the subsequent direct simulations of the four-point bending tests, with the numerically acquired macroscale mechanical responses of irradiated U-10Mo specimens matching the experimental data. After eliminating the effects of fuel porosity, it is found that the values of Young's modulus of dense U-10Mo fuel skeleton decrease with increasing fission density or macroscale porosity, thereby becoming a primary contributor to the degradation of the effective Young's modulus of irradiated U-10Mo fuel. Furthermore, mathematical models for the Young's modulus of irradiated U-10Mo fuel skeleton at room temperature are developed as functions of fission density and macroscale porosity, respectively. The predicted results indicate that the von Mises stress will significantly decrease and the equivalent creep strains might have a distinct increase, when the degradation of Young's modulus of fuel skeleton is incorporated. This work provides a foundation for the high-precise modeling of the irradiation-induced thermo-mechanical behaviors of the U-10Mo-based fuel elements or assemblies.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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