studymcnpandgeant,Student,github

Nuclear Reaction Monte Carlo Simulation Package from WUSTL

Using discrete coordinate approach (SN method) to calculate the neutron flux in simplified one-dimensional geometry.

OpenMC Monte Carlo Code

A method of characteristics code for nuclear reactor physics calculations.

An method of characteristics code with acceleration schemes: CMFD, low order transport.

A Monte Carlo code for simple spectral calculations in nuclear reactor applications.

基于一阶泰勒展开的点堆中子动力学方程求解程序

这里收录比较实用的计算机相关技术书籍，可以在短期之内入门的简单实用教程、一些技术网站以及一些写的比较好的博文，欢迎Fork，你也可以通过Pull Request参与编辑。

PyNE: The Nuclear Engineering Toolkit

A mini-app that extracts the key features of Monte Carlo neutron transport

This is just a toy MC code to get familiar with Monte Carlo process

two dimension

General work related to thermal neutron scattering and the importance of phonon distribution representations

**科学技术大学计算机学院课程资源(https://mbinary.xyz/ustc-cs/)

2021**翻墙软件VPN推荐以及避坑指南，对比SSR机场、蓝灯、WireGuard、V2ray、老王VPN、VPS搭建梯子等科学上网软件与方法，**最新科学上网翻墙VPN梯子下载推荐，稳定好用。

翻墙软件攻略，**VPN推荐指南2020版 - 国内还能用的翻墙VPN就这几个了。科学上网、翻墙工具vpn推荐最新地址。

continuous energy monte carlo neutron transport in general geometries on GPUs

studymcnpandgeant Goto Github PK