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Simulation of irradiation hardening of Zircaloy within plate-type dispersion nuclear fuel elements

机译:板状弥散核燃料元件中锆合金辐照硬化的模拟

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Within plate-type dispersion nuclear fuel elements, the metal matrix and cladding attacked continuously by fast neutrons undergo irradiation hardening, which might have remarkable effects upon the mechanical behaviors within fuel elements. In this paper, with the irradiation hardening effect of metal materials mainly considered together with irradiation growth effect of the cladding, the three-dimensional large-deformation constitutive relations for the metal matrix and cladding are developed. The method of virtual temperature increase in the previous studies is further developed to model the irradiation swelling of fuel particles; the method of anisotropic thermal expansion is introduced to model irradiation growth of the cladding; and a method of multi-step-temperature loading is proposed to simulate the coupling features of irradiation-induced swelling of the fuel particles together with irradiation growth of the cladding. Above all, based on the developed relationship between irradiation growth at certain burnup and the loaded virtual temperatures, with considering that certain burnup corresponds to certain fast neutron fluence, the time-dependent constitutive relation due to irradiation hardening effect is replaced by the virtual-temperature-dependent one which is introduced into the commercial software to simulate the irradiation hardening effects of the matrix and cladding. Numerical simulations of the irradiation-induced mechanical behaviors are implemented with the finite element method in consideration of the micro-structure of the fuel meat. The obtained results indicate that when the irradiation hardening effects are introduced into the constitutive relations of the metal matrix and cladding: (1) higher maximum Mises stresses for certain burnup at the matrix exist with the equivalent plastic strains remaining almost the same at lower burnups; (2) the maximum Mises stresses for certain burnup at the cladding are enhanced while the maximum equivalent plastic strains are reduced; and (3) the maximum first principal stresses for certain burnup at the matrix or the cladding are lower than the ones without the hardening effect, and the differences are found to increase with burnup; and the variation rules of the interfacial stresses are similar.
机译:在板状弥散型核燃料元件中,被快速中子连续攻击的金属基体和包壳经历辐射硬化,这可能对燃料元件内的机械性能产生显着影响。本文主要考虑金属材料的辐照硬化效应以及包层的辐照生长效应,建立了金属基体和包层的三维大变形本构关系。先前研究中虚拟温度升高的方法得到了进一步发展,以模拟燃料颗粒的辐照膨胀。引入各向异性热膨胀的方法来模拟包层的辐照生长。提出了一种多级温度加载的方法,以模拟辐照引起的燃料颗粒膨胀与包覆层辐照生长的耦合特征。最重要的是,基于在一定燃耗下的辐照生长与负载虚拟温度之间发展的关系,考虑到某些燃耗对应于某些快中子注量,由辐照硬化效应引起的时变本构关系被虚温代替。依赖的模型,将其引入商业软件中以模拟基体和覆层的辐射硬化效果。考虑到燃料肉的微观结构,采用有限元方法对辐照引起的机械行为进行了数值模拟。所得结果表明,当将辐射硬化效应引入金属基体与覆层的本构关系时:(1)对于基体某些燃耗,存在较高的最大Mises应力,而当较低燃耗时,等效塑性应变几乎保持相同; (2)增强了包层某些燃尽时的最大米塞斯应力,同时减小了最大等效塑性应变; (3)基体或覆层一定燃耗的最大第一主应力低于没有硬化作用的最大主应力,并且随着燃耗的增加,差异会增大。界面应力的变化规律相似。

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