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裂变碎片Xe对Zr弹性模量影响的多尺度模拟研究
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1.中国核动力研究设计院核反应堆系统设计技术重点实验室;2.上海交通大学材料科学与工程学院

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国家科技部重点研发计划(2022YFB1902402)


Multi-scale Simulation of the Influence of Fission Fragments on the Zr Elastic Modulus
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    摘要:

    锆(Zr)合金具有较小的热中子吸收截面和优良的耐腐蚀性能与力学性能,是核电反应堆的核心部件,其在服役条件下的力学行为对反应堆的安全运行起关键作用。弹性模量是锆合金的关键力学性能之一,影响着锆合金的弹塑性变形。辐照形成空洞,裂变碎片的固溶效应等机制将影响锆合金的弹性模量,进而改变锆合金的力学行为。本文基于第一性原理和相场微弹性理论,结合弹性自洽理论,开展了研究工作,揭示了裂变碎片元素和辐照空洞对Zr弹性模量的影响规律。并建立了弹性模量随辐照损伤剂量和温度变化的定量关系模型,进一步推动了锆合金辐照力学行为领域的研究与发展。

    Abstract:

    Zirconium (Zr) alloy is the core component of nuclear power reactor with small thermal neutron absorption cross section, excellent corrosion resistance and mechanical properties. Its mechanical behaviors play a key role in the safe operation of the reactor under service conditions. The elastic modulus is one of the crucial mechanical properties of Zr alloy, which affects the elastic-plastic deformation. The formation of voids by irradiation and the solid solution effect of fission fragments will affect the elastic modulus of Zr alloy, thereby altering the mechanical behaviors. Based on density functional theory, phase field micro-elasticity theory, and elastic self-consistent, this work has revealed the influence of the fission fragment elements and irradiation voids on the Zr elastic modulus. The quantitative relationship model has been established between the elastic modulus and the changes in irradiation damage dose and temperature, further promoting the research and development in the mechanical behaviors field of Zr alloy irradiation.

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孙志鹏,彭丹珉,张自康,刘桂森,江林丰,李垣明,唐传宝,沈耀.裂变碎片Xe对Zr弹性模量影响的多尺度模拟研究[J].稀有金属材料与工程,,().[Sun Zhipeng, Peng Danmin, Zhang Zikang, Liu Guisen, Jiang Linfeng, Li Yuanming, Tang Chuanbao, Shen Yao. Multi-scale Simulation of the Influence of Fission Fragments on the Zr Elastic Modulus[J]. Rare Metal Materials and Engineering,,().]
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  • 收稿日期:2024-04-17
  • 最后修改日期:2024-07-08
  • 录用日期:2024-07-10
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