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Effects of irradiation hardening and creep on the thermo-mechanical behaviors in inert matrix fuel elements

机译:辐照硬化和蠕变对惰性基质燃料元件热机械行为的影响

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摘要

An inert matrix fuel element consists of metal cladding and a composite fuel meat with the nuclear fuel particles embedded into the metal inert matrix. In order to precisely predict its in-pile thermo-mechanical coupling behaviors, the three-dimensional finite-strain constitutive relation is developed featuring consideration of the irradiation hardening plasticity and irradiation creep for the metal matrix and cladding; accordingly, several ABAQUS subroutines are built and validated to simulate irradiation swelling of the fuel particles and the above irradiation damage effects in the metal materials. Computation of the in-pile thermo-mechanical behaviors evolution is implemented. Compared to the calculation results considering only the irradiation hardening plasticity, the obtained results demonstrate that with the irradiation creep effect further included: (1) the mechanical interaction between the fuel particles and the matrix is weakened; (2) the maximum Mises stress and principal stress in the cladding tend to be very low; (3) similarly, the interfacial tensile stresses at the interface between the fuel meat and cladding also appear to be relatively smaller at higher burnup, and the interfacial shear stresses are close to zero; (4) the thickness increment of the fuel plate becomes comparably larger.
机译:惰性基质燃料元件由金属包壳和复合燃料肉组成,核燃料颗粒嵌入金属惰性基质中。为了精确预测其桩内热力耦合行为,建立了三维有限应变本构关系,考虑了金属基体和覆层的辐照硬化可塑性和辐照蠕变。因此,建立并验证了几个ABAQUS子例程,以模拟燃料颗粒的辐照膨胀和金属材料中的上述辐照损伤效应。实现了桩内热力学行为演化的计算。与仅考虑辐照硬化塑性的计算结果相比,所获得的结果表明,辐照蠕变效应还包括:(1)燃料颗粒与基体之间的机械相互作用减弱; (2)包层中的最大米塞斯应力和主应力往往很低; (3)类似地,在更高的燃耗下,燃料肉和覆层之间的界面处的界面拉应力也似乎相对较小,并且界面剪切应力接近于零; (4)燃料板的厚度增量相对较大。

著录项

  • 来源
    《Mechanics of materials》 |2013年第10期|110-123|共14页
  • 作者单位

    Department of Mechanics and Engineering Science. Fudan University, Shanghai 200433, China;

    Department of Mechanics and Engineering Science. Fudan University, Shanghai 200433, China,Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institution of China, Chengdu 610041, Sichuan, China;

    Department of Mechanics and Engineering Science. Fudan University, Shanghai 200433, China;

    Department of Mechanics and Engineering Science. Fudan University, Shanghai 200433, China;

    Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institution of China, Chengdu 610041, Sichuan, China;

    Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institution of China, Chengdu 610041, Sichuan, China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Inert matrix fuel element; Three-dimensional constitutive relations; Finite strain plasticity; Irradiation damage; Creep; Fern;

    机译:惰性基质燃料元件;三维本构关系;有限应变可塑性;辐射损伤;蠕变;蕨类;

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