continuous energy monte carlo neutron transport in general geometries on GPUs
☆46Jun 8, 2017Updated 8 years ago
Alternatives and similar repositories for warp
Users that are interested in warp are comparing it to the libraries listed below
Sorting:
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆28May 19, 2021Updated 4 years ago
- A C++ Monte Carlo Neutron Transport Code☆20Dec 10, 2025Updated 2 months ago
- Simulation of transmutation and decay in nuclear systems☆35Feb 21, 2026Updated last week
- Tool for converting MCNP input files to OpenMC classes/XML☆53Dec 9, 2025Updated 2 months ago
- Framework for REsearch in Nuclear ScIence and Engineering☆15Sep 8, 2021Updated 4 years ago
- CGMF nuclear fission fragment de-excitation statistical code☆28Mar 26, 2024Updated last year
- Collection of validation scripts, notebooks, results☆11Dec 23, 2025Updated 2 months ago
- Format description for ACE nuclear data files☆22Apr 28, 2022Updated 3 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Jun 26, 2025Updated 8 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Jun 25, 2024Updated last year
- End-to-end python-based supervised machine learning pipeline for ML-augmented nuclear data evaluation.☆23Oct 12, 2024Updated last year
- Direct Accelerated Geometry Monte Carlo Toolkit☆123Feb 16, 2026Updated last week
- NJOY for the 21st Century☆85Jan 22, 2024Updated 2 years ago
- Tools to translate between different CSG geometry types☆41May 28, 2025Updated 9 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…☆42Dec 11, 2024Updated last year
- The Cyclus Nuclear Fuel Cycle Simulator☆86Jan 15, 2026Updated last month
- Large scale scientific simulation engine☆38Nov 9, 2023Updated 2 years ago
- A set of radiation transport mini-applications used for performance optimization on HPC systems.☆29Aug 14, 2018Updated 7 years ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆62Sep 30, 2025Updated 5 months ago
- The Advanced Dimensional Depletion for Engineering of Reactors (ADDER) Software☆20Dec 15, 2025Updated 2 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆42Jan 23, 2026Updated last month
- Stochastic Calculator Of Neutron transport Equation☆56Feb 18, 2026Updated last week
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆32Jan 29, 2026Updated last month
- Native plotting GUI for model design and verification☆65Feb 9, 2026Updated 2 weeks ago
- Sampling nuclear data and uncertainty☆56Updated this week
- NCrystal : a library for thermal neutron transport in crystals and other materials☆47Feb 20, 2026Updated last week
- Monte Carlo Particle Lists☆36Feb 18, 2026Updated last week
- OpenMC wrapped as a Moose App☆16May 1, 2023Updated 2 years ago
- Nuclear data processing with legacy NJOY☆124Jan 20, 2026Updated last month
- A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.☆111Feb 10, 2025Updated last year
- Python for Reactor Kinetics☆35Sep 26, 2025Updated 5 months ago
- An open-source nuclear reactor analysis automation framework that helps design teams increase efficiency and quality☆262Updated this week
- Accelerated Discretized Geometry☆24Updated this week
- Repository for Moltres, a code for simulating Molten Salt Reactors☆78Feb 9, 2026Updated 2 weeks ago
- OpenMC Monte Carlo Code☆24Jan 31, 2025Updated last year
- A library for multiphysics solution transfer. ARCHIVED☆51Nov 27, 2023Updated 2 years ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆43Dec 24, 2025Updated 2 months ago
- Sn neutron transport written mostly in python. For university Sn transport theory class.☆12Aug 23, 2017Updated 8 years ago
- PyNE: The Nuclear Engineering Toolkit☆312Oct 22, 2025Updated 4 months ago