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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。
The Cri SAA was used to numerically simulate the experiment of uniform injection of nuclear fuel (RF) on a TRACY device to study the transient characteristics of the open critical drift of a nuclear fuel solution device. The simulation results are predictive. Cri SAA gives the random characteristics of physical quantities such as the first peak time, the first peak power, the first peak energy release and the total fission energy. The effects of reactivity addition rate and uranium solubility on critical drift are analyzed . An improved Fuchs model for open critical drift analysis is proposed, which helps to understand the open critical drift process.