论文标题
MONC运输代码的状态和范围
Status and Scope of MONC Transport Code
论文作者
论文摘要
$ \ usewissline {\ textbf {mo}} $ nte-carlo $ \ usepline {\ textbf {n}} $ ucleon transport $ \ usepline {\ textbf {c}} $ ode(monc)用于核运输,用于开发几年。建设性固体几何概念是在固体的帮助下应用的。联合,减法和交点布尔操作用于构建异质区域。允许基本体的缩放,旋转和翻译操作构建更复杂的区域。开发了用于晶格的重复结构模块,反应堆和检测器模拟中的核心计算。开发了图形用户界面以及可视化工具,以制作输入,构造和显示几何以及输出数据的分析。低能中子传输模块是使用低于20mev中子能量以下的连续线性插值点中子横截面数据开发的。该代码是基准的,用于模拟加速器驱动的亚临界系统,中子屏蔽,热量和中子通量分布以及关键组件的KEFF。据观察,KEFF的结果在$ \ sim $ 3MK之内与关键组件的实验结果以及从MCNP获得的值一致。
$\underline{\textbf{MO}}$nte-carlo $\underline{\textbf{N}}$ucleon transport $\underline{\textbf{C}}$ode (MONC) for nucleon transport is being developed for several years. Constructive Solid Geometry concept is applied with the help of solid bodies. Union, subtraction and intersection Boolean operations are used to construct heterogeneous zones. Scaling, rotation, and translation operation of the basic bodies are allowed to construct more complex zones. Module of repetitive structure for lattice, core calculations in reactor and detector simulation is developed. Graphical User Interface along with visualization tools is developed to make input, construction and display of geometry, and analysis of output data. Low energy neutron transport module is developed using continuous linearly interpolable point neutron cross section data below 20MeV neutron energy. The code is benchmarked for simulation of accelerator driven sub-critical system, neutron shielding, heat and neutron flux distribution and keff of the critical assemblies. It is observed that results of keff are in agreement within $\sim$ 3mk with experimental results of critical assemblies as well as the values obtained from MCNP.