weft / warpLinks
continuous energy monte carlo neutron transport in general geometries on GPUs
☆45Updated 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☆118Updated 9 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆28Updated 4 years ago
- Native plotting GUI for model design and verification☆64Updated last month
- OpenMC Monte Carlo Code☆23Updated 9 months ago
- Collection of models for reactor physics benchmarks☆57Updated 2 months ago
- Large scale scientific simulation engine☆37Updated 2 years ago
- Collection of scripts for managing data for OpenMC☆38Updated last week
- Stochastic Calculator Of Neutron transport Equation☆51Updated 3 weeks ago
- open-source Sn software☆49Updated this week
- Sampling nuclear data and uncertainty☆53Updated last month
- Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code☆11Updated 3 years ago
- Helios - A C++ Monte Carlo Neutron Transport Code☆20Updated 5 years ago
- Collection of validation scripts, notebooks, results☆11Updated 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
- Tool for converting MCNP input files to OpenMC classes/XML☆50Updated 3 weeks ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated this week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 4 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆81Updated 3 weeks ago
- List of open source projects related to OpenMC☆30Updated 5 months ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Python ENDF Parser☆39Updated 3 weeks ago
- Simulation of transmutation and decay in nuclear systems☆32Updated last week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆34Updated 4 months ago
- Accelerated Discretized Geometry☆18Updated last week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆40Updated last month
- Convert OpenMC Geometry Components to CAD☆20Updated last year