OpenMC Monte Carlo Code
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Updated
Jun 2, 2024 - Python
OpenMC Monte Carlo Code
The main whatisnuclear.com website
Main yt repository
A curated list of open source projects used in nuclear science and engineering
A python package to handle pebble packing and movement in reactor core volumes.
Holds the research group website.
Open Nuclear Reactor Simulator
Online reprocessing for molten salt reactors
Lindsay et al. Introduction to Moltres: An application for simulation of Molten Salt Reactors. Annals of Nuclear Energy. 2018
A suite of parsers designed to make interacting with SERPENT output files simple and flawless
Python Framework for data-driven model Order Reduction of multi-physiCs problEms
The sciantix-official repository contains the SCIANTIX code for inert gas behaviour, together with the validation database and regression files.
MC/DC: Monte Carlo Dynamic Code
Energy-dependent neutron transport Monte Carlo implemented in Rust.
Simple codebase to analyze and download Evaluated Nuclear Data Files (ENDFs).
List of open source projects related to OpenMC
Python package for generating a core, time-dependent geometry for reactor analyses with FRENETIC and FreeFEM++ codes.
Tool for converting MCNP input files to OpenMC classes/XML
A multi isotope enrichment module for the nuclear fuel cycle simulator Cyclus
Package Manager for Nuclear Engineering Development
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