在第四代反应堆的发展中，钍基反应堆（例如钍基熔盐堆）是其中一个重要的研究方向．由于钍的储量大等因素，利用中子诱发232Th发生辐射俘获反应产生233Th是钍基反应堆中的一个重要反应，用于产生易裂变核素233U．本研究采用Monte Carlo方法，定义了一种评价靶材和中子利用效率的综合利用系数，利用多项式拟合得到了综合利用系数和靶材厚度关系，并考虑了不同入射中子数目的影响，最后得到进行此反应的靶材最佳厚度为(1.980±0.002) cm．

In the development of fourthgeneration reactors, thoriumbased reactors, such as thoriumbased molten salt reactors, have emerged as an important research direction. Due to factors such as the abundance of thorium reserves, utilizing neutroninduced 232Th radiation capture reactions to produce 233Th is a crucial reaction in thoriumbased reactors for generating fissile isotope 233U. In this study, Monte Carlo method is employed to define a comprehensive utilization coefficient that evaluates the target material and neutron utilization efficiency. The relationship between the utilization coefficient and target material thickness is obtained through polynomial fitting, considering the influence of different incident neutron numbers. Finally, the optimum target material thickness for this reaction is determined to be (1.980±0.002)cm.