weft / warpLinks
continuous energy monte carlo neutron transport in general geometries on GPUs
☆46Updated 8 years ago
Alternatives and similar repositories for warp
Users that are interested in warp are comparing it to the libraries listed below
Sorting:
- Direct Accelerated Geometry Monte Carlo Toolkit☆120Updated 11 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- Large scale scientific simulation engine☆38Updated 2 years ago
- Collection of models for reactor physics benchmarks☆58Updated 4 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code☆12Updated 3 years ago
- A C++ Monte Carlo Neutron Transport Code☆20Updated last month
- Stochastic Calculator Of Neutron transport Equation☆55Updated 2 weeks ago
- Native plotting GUI for model design and verification☆64Updated 2 weeks ago
- Collection of scripts for managing data for OpenMC☆38Updated last month
- Nuclear data processing with legacy NJOY☆123Updated 2 weeks ago
- Open-source Sn software☆58Updated this week
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Sampling nuclear data and uncertainty☆55Updated 4 months ago
- OpenMC Monte Carlo Code☆24Updated last year
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆24Updated 3 weeks ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 7 months ago
- Tools to translate between different CSG geometry types☆40Updated 8 months ago
- Python ENDF Parser☆39Updated last week
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆28Updated 4 years ago
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆85Updated 2 months ago
- Collection of validation scripts, notebooks, results☆11Updated last month
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆38Updated 7 months ago
- NJOY for the 21st Century☆84Updated 2 years ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆41Updated 2 weeks ago
- Simulation of transmutation and decay in nuclear systems☆35Updated last week
- Tool for converting MCNP input files to OpenMC classes/XML☆53Updated last month