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ATHLET是德国核设施安全评审中心GRS开发的一个重要的反应堆热工水力学分析程序。为了全面评估ATHLET程序应用于清华大学核能与新能源技术研究院建造5MW低温核供热实验堆(NHR-5)的适用性,该文建立了5MW低温供热堆的ATHLET输入模型,以功率自跟随实验为模拟对象进行验证性计算分析。将结果与对应的实验结果、RETRAN-02程序的计算结果进行比较。曲线显示:反应堆上腔体压力、堆芯入口温度的ATHLET计算值和实验值之间的差异分别达到2×10-2M Pa和2.5K。分析结果表明,燃料元件表面过冷沸腾的空泡反应性反馈对取得良好的模拟计算结果有重要作用。
ATHLET is an important reactor thermal hydraulics analysis program developed by GRS, the German Nuclear Facilities Safety Assessment Center. In order to fully evaluate the applicability of the ATHLET program to build a 5MW low temperature nuclear reactor (NHR-5) reactor at the Institute of Nuclear and New Energy Technology, Tsinghua University, an ATHLET input model of a 5MW low temperature heating reactor was established. Follow the experiment for the simulation object to verify the calculation and analysis. The results were compared with the corresponding experimental results, the calculation results of the RETRAN-02 program. The curves show that the difference between the calculated value of the ATHLET and the experimental value of the reactor upper cavity pressure and the temperature of the core inlet reaches 2 × 10 -2 M Pa and 2.5 K, respectively. The results show that the cavitation reactivity feedback of supercooled fuel surface plays an important role in obtaining good simulation results.