In-line (α,n) source sampling methodology for monte carlo radiation transport simulations
In-line (α,n) source sampling methodology for monte carlo radiation transport simulations
复制标题
用于蒙特卡罗辐射传输模拟的在线 (α,n) 源采样方法
DOI：
10.1016/j.net.2017.08.004
复制
发表时间：
2017
影响因子：
2.7
通讯作者：
H. Joo
中科院分区：
文献类型：
--
作者：
D. Griesheimer;A. T. Pavlou;J. T. Thompson;J. Holmes;M. Zerkle;E. Caro;H. Joo
基于α粒子源信息，发展了一种用于连续能蒙特卡罗模拟的（α，n）反应中子在线取样方法。新方法采用连续慢化模型结合（α，n）截面数据来预估α粒子寿命内的中子产额。这消除了与显式带电粒子输运相关的复杂性和计算成本。当与集成的α粒子衰变源采样能力相结合时，所提出的方法提供了一种仅基于问题中的核素清单的（α，n）中子采样的高效且准确的方法，而不需要额外的用户输入。几个算例的计算结果表明，该方法能较好地再现参考实验和计算的（α，n）中子产额和能谱。
A new in-line method for sampling neutrons emitted in (α,n) reactions based on alpha particle source information has been developed for continuous-energy Monte Carlo simulations. The new method uses a continuous-slowing-down model coupled with (α,n) cross section data to precompute the expected neutron yield over the alpha particle lifetime. This eliminates the complexity and computational cost associated with explicit charged particle transport. When combined with an integrated alpha particle decay source sampling capability, the proposed method provides an efficient and accurate method for sampling (α,n) neutrons based solely on nuclide inventories in the problem, with no additional user input required. Results from several example calculations show that the proposed method reproduces the (α,n) neutron yields and energy spectra from reference experiments and calculations.