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An improved structural mechanics model for the FRAPCON nuclear fuel performance code

机译:FRapCON核燃料性能代码的改进结构力学模型

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摘要

In order to provide improved predictions of Pellet Cladding Mechanical Interaction (PCMI) for the FRAPCON nuclear fuel performance code, a new model, the FRAPCON Radial-Axial Soft Pellet (FRASP) model, was developed. This new model uses 1.5D structural mechanics to represent both the fuel pellet and cladding along with their interaction via interfacial forces. The fuel pellet and cladding are modeled as concentric annular cylinders using similar governing equations with slight differences to allow for cracking of the semi-brittle fuel matrix and plastic behavior in a ductile cladding. By accounting for the structural mechanics of the fuel pellet, FRASP allows for stress-induced deformations which were previously unattainable with the rigid pellet model used by FRAPCON. Because of the significant differences between FRAPCON's previous mechanical model, FRACASI, and FRASP, simply replacing the treatment of PCMI within the code was not a viable option. This led to a complete replacement of FRACAS-I and all associated fuel rod structural calculations. Feedback effects are likely to result from such a major change due to the complexity of nuclear fuel simulation. The potential for these feedback effects dictated a preliminary validation of FRASP against FRACAS-I for typical case. This evaluation was not limited to the investigation of mechanical parameters, but covered a wide variety of predicted parameters by the new and unaltered versions of FRAPCON. The differences which were found in this validation were limited in nature and easily attributable to the differing assumptions of FRASP and FRACAS-I. The newly developed mechanical model was used with the improved fuel behavior models of FRAPCON-EP (Enhanced Performance) to assess the mechanical behavior of fuel rods with a composite silicon carbide (SiC) cladding under Pressurized Water Reactor (PWR) conditions. The fuel rod designs were selected to match previously chosen values for both solid and annular fuel pellets under current and uprated power conditions. Unlike FRACAS-I, which is hindered by the rigid pellet model, FRASP was able to successfully analyze PCMI behavior with the more rigid SiC, even though "hard contact" of the fuel and cladding was encountered. Simulations using the improved models showed that the SiC clad fuel rods may not provide adequate safety margins at the desired burnup, or simply fail to achieve their desired final burnup. Previous analyses which relied on FRAPCON-3.3 may have been overly optimistic in this regard. The new, more conservative predictions are largely due to FRASP's treatment of the inner radius of the annular fuel pellets, which was assumed not to change in previous versions of FRAPCON. These new findings suggest that SiC fuel rod general design and operation require further optimization.
机译:为了提供有关FRAPCON核燃料性能代码的球团覆层机械相互作用(PCMI)的改进预测,开发了一种新模型FRAPCON径向-轴向软球团(FRASP)模型。这个新模型使用1.5D结构力学来表示燃料颗粒和包层以及它们之间的相互作用。使用相似的控制方程,将燃料芯块和包壳建模为同心环形圆柱体,但存在细微差别,以允许半脆性燃料基体开裂和延性包壳中的塑性行为。通过考虑燃料芯块的结构力学,FRASP可以实现由应力引起的变形,这是FRAPCON使用的刚性芯块模型以前无法实现的。由于FRAPCON以前的机械模型,FRACASI和FRASP之间存在显着差异,因此仅替换代码中的PCMI处理不是一个可行的选择。这导致FRACAS-I的完全替代以及所有相关的燃料棒结构计算。由于核燃料模拟的复杂性,这种重大变化可能会产生反馈效应。这些反馈效应的潜力决定了针对典型案例针对FRACAS-I进行FRASP的初步验证。该评估不仅限于机械参数的研究,还涵盖了新的和未更改的FRAPCON版本的各种预测参数。在此验证中发现的差异本质上是有限的,很容易归因于FRASP和FRACAS-I的不同假设。新开发的机械模型与FRAPCON-EP(增强性能)的改进燃料行为模型一起使用,以评估在加压水反应堆(PWR)条件下具有复合碳化硅(SiC)包层的燃料棒的机械行为。选择燃料棒设计以使其与当前和当前功率条件下的固体和环形燃料芯块的先前选择值相匹配。与FRACAS-I(受刚性颗粒模型阻碍)不同,即使遇到燃料和覆层的“硬接触”,FRASP仍可以使用刚性更高的SiC成功分析PCMI行为。使用改进模型进行的仿真表明,SiC包覆燃料棒可能无法在所需燃尽时提供足够的安全裕度,或者根本无法实现其所需的最终燃尽。在这方面,以前依靠FRAPCON-3.3进行的分析可能过于乐观。新的,更保守的预测很大程度上是由于FRASP对环形燃料芯块的内半径的处理,而在以前的FRAPCON版本中,该假设没有改变。这些新发现表明,SiC燃料棒的总体设计和操作需要进一步优化。

著录项

  • 作者

    Mieloszyk Alexander James;

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  • 年度 2012
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  • 原文格式 PDF
  • 正文语种 eng
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