lanl / CGMFLinks
CGMF nuclear fission fragment de-excitation statistical code
☆28Updated last year
Alternatives and similar repositories for CGMF
Users that are interested in CGMF are comparing it to the libraries listed below
Sorting:
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last week
- List of open source projects related to OpenMC☆30Updated 6 months ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆42Updated last year
- Native plotting GUI for model design and verification☆64Updated 2 weeks ago
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆28Updated 4 years ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 2 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated 3 weeks ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Stochastic Calculator Of Neutron transport Equation☆53Updated this week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated this week
- Accelerated Discretized Geometry☆19Updated last week
- Open-source Sn software☆52Updated last week
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 5 months ago
- Nuclear data processing with legacy NJOY☆122Updated 3 months ago
- NJOY for the 21st Century☆84Updated last year
- Tools to translate between different CSG geometry types☆40Updated 6 months ago
- Collection of scripts for managing data for OpenMC☆38Updated last week
- Framework for REsearch in Nuclear ScIence and Engineering☆15Updated 4 years ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆24Updated 6 months ago
- Python ENDF Parser☆39Updated last month
- Sampling nuclear data and uncertainty☆53Updated 2 months ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last week
- Computational inputs, reference outputs and experimental data for V&V systems☆15Updated 2 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week