OpenNTP: Implementation of the SN method in cartesian 2D geometry and the CP method in cylindrical and spherical 1D geometry,Computer Physics Communications

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OpenNTP: Implementation of the SN method in cartesian 2D geometry and the CP method in cylindrical and spherical 1D geometry
Computer Physics Communications ( IF 6.3 ) Pub Date : 2020-12-31 , DOI: 10.1016/j.cpc.2020.107812
M. Lahdour , T. El Bardouni , O. El Hajjaji , E. Chakir , H. Ziani , Jamal Al Zain , E. Chham , M. El Barbari

This paper presents the implementation of the discrete ordinates method (S $_{N}$ ) in 2D cartesian geometry and the collision probability method (CP) in cylindrical and spherical 1D geometry in OpenNTP code (Open Neutron Transport Package). This code is a pedagogical tool for computer analysis of nuclear reactors. Its main features are as follows: a free software with an open source, it solves the neutron transport equation to a few steady-state groups on a grid structured in one or two spatial dimensions with an isotropic and anisotropic dispersion source, and any new calculation method and algorithm would be easy to implement in this proposed code. Also, the code offers the possibility to calculate the main parameters of nuclear reactors such as the multiplication factor and the distribution of the scalar and angular neutron fluxes. Additional parameters, like the reaction rates, the pin power distribution and the boundary currents are also calculated. Moreover, a graphical user interface written in Python 3 programming language has been developed to simplify the use of OpenNTP. Some applications of the OpenNTP code have been compared on the one hand with the Monte Carlo OpenMC and MCNP6.1 codes and the WIMSD-5B lattice transport code, on the other hand. Numerical results are given to illustrate the accuracy of the OpenNTP code.

Program summary

Program Title: OpenNTP, version 1.2

CPC Library link to program files: http://dx.doi.org/10.17632/gm2b6799j6.1

Developer’s repository link: https://github.com/mohamedlahdour/OpenNTP

Licensing provisions: GPLv2

Programming language: fortran90 and Python 3

External routines/libraries: NumPy, Matplotlib, PyQt5, f2py

Nature of problem: Solving the steady-state multigroup neutron transport equation by different methods in one, or two spatial dimensions.

Solution method: the characteristic method (MOC), the discrete ordinate (S $_{N}$ ) method and the collision probability method (CP)

中文翻译：

OpenNTP：S的实现 $_{ñ}$ 笛卡尔2D几何中的几何方法以及圆柱和球形一维几何中的CP方法

本文介绍了离散坐标法（S $_{ñ}$ ）在2D笛卡尔几何中使用，并且在OpenNTP代码（Open Neutron运输包装）中在圆柱和球形1D几何中使用碰撞概率方法（CP）。该代码是用于核反应堆计算机分析的教学工具。它的主要特征如下：具有开源功能的免费软件，它将中子输运方程求解到具有一维或二维空间各向同性和各向异性弥散源的网格上的几个稳态组，以及任何新的计算方法该方法和算法将很容易在此建议的代码中实现。此外，该代码还提供了计算核反应堆主要参数的可能性，例如乘数，标量和角中子通量的分布。其他参数，例如反应速度，还计算了引脚功率分布和边界电流。此外，已经开发了用Python 3编程语言编写的图形用户界面，以简化OpenNTP的使用。一方面，已将OpenNTP代码的某些应用与蒙特卡罗OpenMC和MCNP6.1代码以及WIMSD-5B晶格传输代码进行了比较。数值结果表明了OpenNTP代码的准确性。