OpenMC Monte Carlo Code
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Updated
Jun 29, 2024 - Python
OpenMC Monte Carlo Code
Main yt repository
Energy-dependent neutron transport Monte Carlo implemented in Rust.
A repository to hold transition scenarios with Cyclus.
A multi isotope enrichment module for the nuclear fuel cycle simulator Cyclus
The main whatisnuclear.com website
Python package for generating a core, time-dependent geometry for reactor analyses with FRENETIC and FreeFEM++ codes.
A curated list of open source projects used in nuclear science and engineering
A suite of parsers designed to make interacting with SERPENT output files simple and flawless
MC/DC: Monte Carlo Dynamic Code
Holds the research group website.
List of open source projects related to OpenMC
Python Framework for data-driven model Order Reduction of multi-physiCs problEms
A python package to handle pebble packing and movement in reactor core volumes.
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
The sciantix-official repository contains the SCIANTIX code for inert gas behaviour, together with the validation database and regression files.
Simple codebase to analyze and download Evaluated Nuclear Data Files (ENDFs).
Tool for converting MCNP input files to OpenMC classes/XML
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