fispact / SPECTRA-PKALinks
primary knock-on atom (PKA) spectrum evaluator
☆19Updated 2 months ago
Alternatives and similar repositories for SPECTRA-PKA
Users that are interested in SPECTRA-PKA are comparing it to the libraries listed below
Sorting:
- NCrystal : a library for thermal neutron transport in crystals and other materials☆45Updated this week
- NJOY for the 21st Century☆84Updated last year
- Nuclear data processing with legacy NJOY☆119Updated 2 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆50Updated 3 weeks ago
- Python ENDF Parser☆39Updated 3 weeks ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated this week
- ☆86Updated last year
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years 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
- List of open source projects related to OpenMC☆29Updated 5 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated last month
- Native plotting GUI for model design and verification☆64Updated last month
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆80Updated 3 weeks ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 4 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 months ago
- Tools to translate between different CSG geometry types☆40Updated 5 months ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆32Updated 3 weeks ago
- Toolkit for working with ACE-formatted data files☆30Updated 2 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Convert OpenMC Geometry Components to CAD☆20Updated 11 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 4 months ago
- Catalogs a plethora of reactor inputs for OpenMC☆34Updated 8 months ago
- Stochastic Calculator Of Neutron transport Equation☆51Updated 3 weeks ago
- Sampling nuclear data and uncertainty☆53Updated last month
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆40Updated last month
- Collection of scripts for managing data for OpenMC☆37Updated last week
- Format description for ACE nuclear data files☆22Updated 3 years ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated last month