Alternatives and similar repositories for ADPRES:

Users that are interested in ADPRES are comparing it to the libraries listed below

• imronuke / KOMODO
  Open Nuclear Reactor Simulator
  ☆52Updated 8 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆39Updated 3 weeks ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆29Updated last month
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆55Updated last month
• FRENSIE / FRENSIE
  Framework for REsearch in Nuclear ScIence and Engineering
  ☆14Updated 3 years ago
• NCSU-NCSG / THOR
  THOR is a radiation transport code for unstructured meshes.
  ☆11Updated 5 months ago
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 7 months ago
• arfc / moltres
  Repository for Moltres, a code for simulating Molten Salt Reactors
  ☆67Updated last week
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆51Updated 4 months ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆109Updated last week
• idaholab / virtual_test_bed
  The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
  ☆51Updated this week
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• weft / warp
  continuous energy monte carlo neutron transport in general geometries on GPUs
  ☆43Updated 7 years ago
• SlaybaughLab / BART
  A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.
  ☆27Updated 3 years ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆55Updated last week
• DrRyanMc / CompNucEng
  This repository holds codes from the book Computational Nuclear Engineering and Radiological Science with Python
  ☆15Updated 4 years ago
• CEMeNT-PSAAP / MCDC
  MC/DC: Monte Carlo Dynamic Code
  ☆29Updated this week
• aims-umich / pyMAISE
  Machine learning and artificial intelligence benchmarking library for nuclear engineering applications.
  ☆25Updated last week
• openmc-data-storage / isotope-xs-plotter
  XSPlot - Neutron cross section plotter for isotopes
  ☆14Updated last year
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆17Updated last year
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆50Updated last month
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆25Updated 5 months ago
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆23Updated 4 months ago
• pellegre / helios
  Helios - A C++ Monte Carlo Neutron Transport Code
  ☆19Updated 4 years ago
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆100Updated this week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• openmc-dev / openmc-notebooks
  Example Jupyter notebooks for OpenMC
  ☆35Updated 3 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆25Updated this week
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 5 months ago