Thorium is the primary candidate fuel in Thorium-based Molten Salt Reactor (TMSR) and Accelerator Driven System (ADS). However, to utilize Thorium in the reactor and accelerator systems, nuclear data in the literature are not sufficient for neutron-induced fission reaction process. Therefore, we estimated neutron fission cross-section σ (mb), independent Y (A) and primary fission fragment yield YI(A), mass-dependent average neutron multiplicity ν̄(A), energy-dependent average neutron multiplicity ν̄(E) and neutron emission multiplicity distribution ν of 232Th for different neutron incident energy values, 1 MeV, 1.5 MeV, 3 MeV, 5.5 MeV, 7.7 MeV, 10 MeV, 14.8 MeV and 20 MeV, where the energy region is important for the reactor and accelerator systems used in the industry. The obtained results are compared with experimental data obtained from the literature and are discussed for each energy value.

中文翻译：

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钍基熔盐反应堆和加速器驱动系统的裂变产率和截面估算

钍是钍基熔盐反应堆 (TMSR) 和加速器驱动系统 (ADS) 的主要候选燃料。然而，为了在反应堆和加速器系统中使用钍，文献中的核数据不足以用于中子诱导的裂变反应过程。因此，我们估计了中子裂变截面σ(mb)，独立的是 (一种)和初级裂变碎片产量是一世(一种), 与质量相关的平均中子多重度ν̄(一种), 能量相关的平均中子多重度ν̄(乙)和中子发射多重分布ν的232钍对于不同的中子入射能量值，1 MeV、1.5 MeV、3 MeV、5.5 MeV、7.7 MeV、10 MeV、14.8 MeV 和 20 MeV，其中能量区域对于工业中使用的反应堆和加速器系统很重要。将获得的结果与从文献中获得的实验数据进行比较，并对每个能量值进行讨论。