中文摘要：

使用临界漂移分析程序（Cri SAA）对TRACY装置上的匀速注入核燃料溶液（RF）实验进行数值模拟,研究核燃料溶液装置开放临界漂移的瞬态特征,模拟结果是预测性的。Cri SAA给出实验的第一次峰时间、第一次峰功率、第一次峰释能和总裂变能等物理量的随机性特征,分析了反应性添加速度、铀溶度对临界漂移的影响。提出适用于开放临界漂移分析的改进的Fuchs模型,该模型有助于理解开放临界漂移过程。

英文摘要：

Ramp Feed experiments performed on TRACY are simulated with the code CriSAA which is used for the criticality excursion analysis. The transient characteristics of open criticality excursions are studied. The predictive results are shown. The statistics characteristics, including time and energy to first peak, power of first peak and the total energy, are obtained by simulations. The effects of the reactivity insertion rate and the uranium concentration on the criticality excursion are analyzed. Fuchs model are improved to be suitable for open criticality excursion in this paper. It is helpful to understand the open excursion.