在RTOP-CA规范中模拟(U, Gd)O2燃料元件的热力学行为

V. Likhanskii, A. Sorokin, V. Zborovskii, K. Ulibyshev, A. Strozhuk, I. Chernov
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摘要

本文介绍了为模拟(U, Gd)O2燃料棒的性能而设计的RTOP-CA代码模型,并给出了在Halden研究堆和WWER燃料辐照后检验中获得的实验数据进行程序验证的实例。运行WWER燃料的经验表明,(U, Gd)O2燃料元件和UO2燃料棒在第一次和第二次燃料循环期间的热力学行为是不同的。特别是,与UO2燃料元件相比,(U, Gd)O2燃料棒包壳长度的加速增加是可能的。为了模拟(U, Gd)O2燃料棒在RTOP-CA规范下的辐照行为,建立了描述铀-钆燃料特性的模型。为了计算RTOP-CA规范中(U, Gd)O2燃料棒的放热演化,建立了钆同位素燃耗模型。开发的模型可以在不使用详细的中子物理计算的情况下,模拟钆的燃耗和沿球团半径产生热量的演变。该模型考虑了氧化钆含量对燃料热物理和机械性能的影响。用RTOP-CA程序计算的结果与在Halden试验中得到的中心燃料温度、(U, Gd)O2燃料棒内气体压力、燃料柱和包壳伸长率的动力学结果吻合较好。为了模拟核电厂燃料运行初期(U, Gd)O2燃料棒与标准WWER燃料元件相比的加速伸长,在RTOP-CA规范中,考虑球团排列不一致的情况,建立了球团与包壳的力学相互作用模型。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
SIMULATION OF THE THERMOMECHANICAL BEHAVIOR OF (U, Gd)O2 FUEL ELEMENTS IN THE RTOP-CA CODE
The paper presents a description of the RTOP-CA code models designed for simulating the behavior of (U, Gd)O2 fuel rods, presents the examples of program verification using experimental data obtained at the research reactor in Halden and in the post-irradiation examinations of WWER fuel. The experience of operating WWER fuel has shown that differences in the thermomechanical behavior of (U, Gd)O2 fuel elements and UO2 fuel rods during the first - second fuel cycles can be observed. In particular, an accelerated increase in the length of the (U, Gd)O2 fuel rod cladding as compared to UO2 fuel elements is possible. To simulate the behavior of (U, Gd)O2 fuel rods under irradiation in the RTOP-CA code, models that describe the features of uranium-gadolinium fuel were developed. To calculate the evolution of heat release in (U, Gd)O2 fuel rods in the RTOP-CA code, a model of burnup of gadolinium isotopes was implemented. The developed model makes it possible, without using of detailed neutron-physical calculations, to simulate the burnup of gadolinium and the evolution of heat generation along the radius of the pellets. The models take into account the effect of the gadolinium oxide content on the thermophysical and mechanical properties of the fuel. The calculations performed using the RTOP-CA code are in good agreement with the results obtained during the experiments in Halden on the dynamics of the central fuel temperature, gas pressure in the (U, Gd)O2 fuel rod, and the elongation of the fuel column and cladding. To simulate the accelerated elongation of (U, Gd)O2 fuel rods in comparison with standard WWER fuel elements at the initial stages of fuel operation at nuclear power plants in the RTOP-CA code, a model of mechanical interaction of pellets and cladding was developed taking into account the misaligned arrangement of pellets.
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