ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers coupling with the open-source transport code OpenMC.

our next generation fast and scalable CFD code

ENRICO: Exascale Nuclear Reactor Investigative COde

FitsGeo - Python 3 package for PHITS geometry development and visualization

Native plotting GUI for model design and verification

A utility code for generating material cards for MCNP

Creates a plasma source as an openmc.source object from input parameters that describe the plasma

Tools to translate between different CSG geometry types

ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Bakkali & Tarek EL Bardouni, members of Radiation and Nuclear …

An automatic markdown-based conversion of the FreeCAD wiki. Please no pull requests for the time being, edit the wiki instead, thanks!

GPU Accelerated Voxelization Framework for 3D CAD models.

Machine Learning techniques that analyse Forex market.

Forex Robot for automated trading

An adaptive model for prediction of one day ahead foreign currency exchange rates using machine learning algorithms

Using Machine Learning for live currency trading

Predicting forex binary options using time series data and machine learning

Predicting Forex Future Price with Machine Learning

Simple version of auto forex trader build upon the concept of DQN

A module to build Probability of Detection for Non Destructive Testing

Users manual for NJOY2016

NJOY for the 21st Century

🎓 Path to a free self-taught education in Computer Science!

X-Ray Reflectivity Simulator

Matlab examples for Wasatch Photonics spectrometers

OpenMC Monte Carlo Code

Multiphysics Object Oriented Simulation Environment

An open-source nuclear reactor analysis automation framework that helps design teams increase efficiency and quality