inr-kit / numjuggler
Tool to rename cells, surfaces, materials and universes in MCNP input files.
☆11Updated last year
Related projects ⓘ
Alternatives and complementary repositories for numjuggler
- ☆67Updated 5 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆57Updated last month
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆32Updated this week
- Python Interface and Utility Functions for MCNP6☆19Updated 7 years ago
- Some Monte Carlo tools☆45Updated this week
- Monte Carlo Particle Lists☆29Updated 8 months ago
- a companion for writing MCNP input decks☆11Updated 3 years ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆104Updated last week
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 2 years ago
- JADE, a novel nuclear data libraries V&V tool☆23Updated this week
- Tool for converting MCNP input files to OpenMC classes/XML☆36Updated 3 weeks ago
- A utility code for generating material cards for MCNP☆20Updated 3 years ago
- Convert MCNP input files to a general CAD format☆34Updated 7 months ago
- Tools to translate between different CSG geometry types☆35Updated last year
- Sampling nuclear data and uncertainty☆48Updated last month
- A Python package for parsing FISPACT-II output☆25Updated 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
- A visualizer based on POVRAY to create visualizations of MCNPX input files without the need for MCNPX (created by Nick Michiels.)☆12Updated 12 years ago
- Native plotting GUI for model design and verification☆48Updated 3 weeks ago
- Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis☆13Updated 3 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Collection of scripts for managing data for OpenMC☆28Updated 11 months ago
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆52Updated 5 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆34Updated 3 weeks ago
- NCrystal : a library for thermal neutron transport in crystals and other materials☆41Updated this week
- MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.☆9Updated 4 months ago
- OpenMC Monte Carlo Code☆14Updated 2 months ago
- List of open source projects related to OpenMC☆21Updated 2 months ago
- Python ENDF Parser☆26Updated 3 months ago