OpenMC Monte Carlo Code
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Updated
Jul 19, 2024 - Python
OpenMC Monte Carlo Code
Main yt repository
A suite of parsers designed to make interacting with SERPENT output files simple and flawless
Tool for converting MCNP input files to OpenMC classes/XML
MC/DC: Monte Carlo Dynamic Code
Create a surrogate ANN/GBR/GPR/SVR model for regression of nuclear reactor power distribution
DIF3D plugin to the ARMI nuclear reactor analysis framework
The package for reading mcnp input in a pythonic way
Some code for my Physics of Fission Reactors model analysis reports, written in MATLAB and Python
Open source Bateman Solver based on LSODE
This GUI and terminal based program attempts to analyze both qualitative and quantitative characteristics of nuclear reactors. Currently can be done in GUI or in terminal. GUI tkinter is unable to conduct analysis on qualitative characteristics and does not have a scroll bar (two things I was unable to complete).
Generalized machine learning data-set builder for nuclear cross-section models
A pretty viewer for XSM files generated by DRAGON/DONJON or APOLLO neutronic codes
Tally table is a simple GUI program which extracts user defined tallies from a MCNP output.
Holds teaching nodes for the Nuclear Engineering Curriculum Exchange (NECX)
Neutron spectrum regrouping and adjustment tools.
A python library to allow ease of data reduction and data viewing for MCNP output file
Python scripts for Spent Nuclear Fuel Analysis, using SCALE/TRITON output files.
A python package to handle pebble packing and movement in reactor core volumes.
Development of background radiation monitoring with IoT based device
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