mctools / mcpl
Monte Carlo Particle Lists
☆29Updated 8 months ago
Related projects ⓘ
Alternatives and complementary repositories for mcpl
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆57Updated 2 weeks ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆34Updated last week
- ☆67Updated 5 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆36Updated 2 weeks ago
- Sampling nuclear data and uncertainty☆48Updated last month
- A Python package for parsing FISPACT-II output☆25Updated 8 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆32Updated this week
- Tools to translate between different CSG geometry types☆35Updated last year
- List of open source projects related to OpenMC☆20Updated 2 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆24Updated 2 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆12Updated 5 months ago
- OpenMC Monte Carlo Code☆14Updated 2 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆52Updated 4 months ago
- Python ENDF Parser☆26Updated 3 months ago
- Simulation of transmutation and decay in nuclear systems☆27Updated 2 months ago
- ENDF/B pre-processing codes (PREPRO)☆16Updated last year
- Stochastic Calculator Of Neutron transport Equation☆35Updated last month
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆20Updated 3 weeks ago
- ☆17Updated 2 months ago
- JADE, a novel nuclear data libraries V&V tool☆23Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Native plotting GUI for model design and verification☆47Updated 2 weeks ago
- Framework for REsearch in Nuclear ScIence and Engineering☆13Updated 3 years ago
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 2 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆36Updated 4 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆20Updated last month
- Some Monte Carlo tools☆45Updated 2 weeks ago
- Meshing library for nuclear workflows☆42Updated last month
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆25Updated last month
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆28Updated last month