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Argonne National Laboratory
- Denver, CO, USA
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Openmc-FEnicsx for muLtiphysics tutorIAl
A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
Native plotting GUI for model design and verification
A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
MontePy is a Python library (API) to read, edit, and write MCNP input files.
Collection of models for reactor physics benchmarks
The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
Repository for Moltres, a code for simulating Molten Salt Reactors
Multiphysics Object Oriented Simulation Environment
The official repository for ROOT: analyzing, storing and visualizing big data, scientifically
Geant4 toolkit for the simulation of the passage of particles through matter - NIM A 506 (2003) 250-303
Aer is a high performance simulator for quantum circuits that includes noise models
A method of characteristics code for nuclear reactor physics calculations.
A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
Toolkit for reading and interacting with ENDF-6 formatted files
Samples for CUDA Developers which demonstrates features in CUDA Toolkit
Paper at 2020 ANS Winter Meeting on energy deposition in OpenMC
Advanced Samples for the NVIDIA OptiX 7 Ray Tracing SDK
A suite of parsers designed to make interacting with SERPENT output files simple and flawless