Alternatives and similar repositories for adder

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

• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆53Updated last week
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated this week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 6 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 2 months ago
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆21Updated 5 months ago
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆24Updated 6 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 6 months ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆33Updated 5 months ago
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆120Updated last week
• idaholab / virtual_test_bed
  The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
  ☆63Updated last week
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last month
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated last month
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆19Updated last week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆40Updated 2 months ago
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆22Updated 3 years ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆34Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆66Updated 2 years ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆52Updated last week
• mohamedlahdour / OpenNTP
  In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.
  ☆15Updated 5 years ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated last year
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• ezsolti / RFP
  ☆32Updated 4 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆17Updated last month
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated 2 years ago
• Open-Sn / opensn
  open-source Sn software
  ☆50Updated last week
• SlaybaughLab / BART
  A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.
  ☆28Updated 4 years ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 3 years ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆81Updated this week