NuclearData / ACEFormatLinks
Format description for ACE nuclear data files
☆22Updated 3 years ago
Alternatives and similar repositories for ACEFormat
Users that are interested in ACEFormat are comparing it to the libraries listed below
Sorting:
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Tools to translate between different CSG geometry types☆40Updated 6 months ago
- Python ENDF Parser☆39Updated last month
- NJOY for the 21st Century☆84Updated last year
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated 3 weeks 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 11 months ago
- Native plotting GUI for model design and verification☆64Updated last week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 2 months ago
- Toolkit for working with ACE-formatted data files☆30Updated 3 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 months ago
- List of open source projects related to OpenMC☆30Updated 6 months ago
- Collection of scripts for managing data for OpenMC☆38Updated this week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 5 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Stochastic Calculator Of Neutron transport Equation☆53Updated last week
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆28Updated 4 years ago
- OpenMC Monte Carlo Code☆23Updated 10 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 5 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆32Updated last month
- Nuclear data processing with legacy NJOY☆121Updated 3 months ago
- Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code☆11Updated 3 years ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆24Updated 6 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Sampling nuclear data and uncertainty☆53Updated 2 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆81Updated this week