inr-kit / numjuggler
Tool to rename cells, surfaces, materials and universes in MCNP input files.
☆11Updated 2 years ago
Alternatives and similar repositories for numjuggler:
Users that are interested in numjuggler are comparing it to the libraries listed below
- ☆77Updated 10 months ago
- a companion for writing MCNP input decks☆12Updated 4 years ago
- Some Monte Carlo tools☆48Updated last month
- Monte Carlo Particle Lists☆30Updated this week
- A utility code for generating material cards for MCNP☆21Updated 4 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆41Updated this week
- Python Interface and Utility Functions for MCNP6☆20Updated 8 years ago
- JADE, a novel nuclear data libraries V&V tool☆26Updated this week
- Collection of scripts for managing data for OpenMC☆31Updated 3 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆67Updated last week
- Convert MCNP input files to a general CAD format☆35Updated last year
- MCNP(X) project builder using C++☆15Updated this week
- API for parsing and post-processing many MC simulations related files☆15Updated 2 weeks ago
- OpenMC Monte Carlo Code☆17Updated 2 months ago
- Tools to translate between different CSG geometry types☆36Updated last year
- Tool for converting MCNP input files to OpenMC classes/XML☆40Updated 2 months ago
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 2 months ago
- Native plotting GUI for model design and verification☆57Updated 3 months ago
- A Python package for parsing FISPACT-II output☆28Updated this week
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 2 years ago
- A visualizer based on POVRAY to create visualizations of MCNPX input files without the need for MCNPX (created by Nick Michiels.)☆13Updated 12 years ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆39Updated 3 weeks ago
- Toolkit for working with ACE-formatted data files☆28Updated 2 weeks ago
- Sampling nuclear data and uncertainty☆51Updated 3 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- NCrystal : a library for thermal neutron transport in crystals and other materials☆45Updated last week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated this week
- Python ENDF Parser☆32Updated 8 months ago
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆13Updated 7 years ago