OpenMC Monte Carlo Code
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Updated
Jul 30, 2024 - Python
OpenMC Monte Carlo Code
MC/DC: Monte Carlo Dynamic Code
Energy-dependent neutron transport Monte Carlo implemented in Rust.
Main yt repository
Python Framework for data-driven model Order Reduction of multi-physiCs problEms
Tools to work with MCNP models and results
The main whatisnuclear.com website
An attempt at developing an optimized control rod design for a nuclear reactor using a genetic algorithm and perturbation theory of the simple neutron diffusion equation model.
Python package for generating a core, time-dependent geometry for reactor analyses with FRENETIC and FreeFEM++ codes.
Holds the research group website.
A set of MATLAB scripts that runs SRIM2013 natively within MATLAB for displacement-per-atom (DPA) calculations
A repository to hold transition scenarios with Cyclus.
Papillon Nuclear Data Library
A multi isotope enrichment module for the nuclear fuel cycle simulator Cyclus
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
List of open source projects related to OpenMC
A python package to handle pebble packing and movement in reactor core volumes.
Open Nuclear Reactor Simulator
Online reprocessing for molten salt reactors
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