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Tool for converting MCNP input files to OpenMC classes/XML
Makes data and post-processing scripts available for reproducibility to support publication.
The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
Data Collection from the Systems for Nuclear Auxiliary Power (SNAP) program
MOUSE is a tool for estimating microreactor costs by integrating design calculations and economic analysis. It evaluates the impact of technological changes and economic parameters on microreactor …
Notepad++ Linux Fork
Notepad++ official repository
Direct Simulation Monte Carlo transport of charged and neutral particles
Code for automated production of a fusion materials activation handbook using OpenMC. Containing simulated activity, dose and decay heat characteristics for elements and materials exposed to neutro…
PANTERA is an open-source software for the simulation of nonequilibrium gas and plasma flows based on the Direct Simulation Monte Carlo and Particle-in-Cell methods.
Public development project of the SPARTA DSMC software package http://sparta.github.io
Spec-driven development (SDD) for AI coding assistants.
Geant4 toolkit for the simulation of the passage of particles through matter - NIM A 506 (2003) 250-303
Celeritas is a new Monte Carlo transport code designed to accelerate scientific discovery in high energy physics by improving detector simulation throughput and energy efficiency using GPUs.
Contains documentation, scripts (MCNP, SCALE, Python), ect for the Energy Tuning Assembly Experiment at the National Ignition Facility
The home of the McStas (neutrons) and McXtrace (x-rays) Monte-Carlo ray-tracing instrument simulation codes.
API for parsing and post-processing many MC simulations related files
Benchmark problems and input decks for OpenMC.
An open-source tool that converts EPICS datasets (EEDL, EADL, and EPDL) into structured HDF5 files, making evaluated electron-photon coupled physics data easy to use in Python-based simulations, an…
Directional Relativistic Spectrum Simulator (DRESS) for fusion reactions.
Python package for processing nuclear data distribution in ACE and ENDF format into HDF5 format for use in OpenMC. Adapted from the openmc data repo.
Python package for reading, writing, verifying and translating ENDF-6 formatted files
A python-based graphical user interface for the ion-solid interaction code SDTrimSP
My attempt at creating an OpenMC depletion chain file with isomer branching ratios for more than (n,gamma) reactions. Data extracted from JENDL-5 library at 14MeV
This repository holds various models and benchmarks
MCNP6 source subroutine for simulating D-T neutrons in Ti-T Target