Alternatives and similar repositories for moltres

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

• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆65Updated 2 years ago
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆120Updated this week
• idaholab / virtual_test_bed
  The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
  ☆63Updated this week
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• cyclus / cyclus
  The Cyclus Nuclear Fuel Cycle Simulator
  ☆85Updated last month
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆20Updated 3 months ago
• CEMeNT-PSAAP / MCDC
  MC/DC: Monte Carlo Dynamic Code
  ☆45Updated this week
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆33Updated 4 months ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆116Updated 8 months ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆35Updated 9 months ago
• arfc / saltproc
  Online reprocessing for molten salt reactors
  ☆21Updated 6 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated last month
• SlaybaughLab / BART
  A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.
  ☆28Updated 4 years ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆63Updated last week
• openmsr / msre
  detailed cad model of the msre
  ☆39Updated this week
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆51Updated this week
• weft / warp
  continuous energy monte carlo neutron transport in general geometries on GPUs
  ☆45Updated 8 years ago
• mit-crpg / OpenMOC
  A method of characteristics code for nuclear reactor physics calculations.
  ☆169Updated last year
• jlanversin / ONIX
  ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…
  ☆41Updated 10 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆48Updated last week
• svalinn / ALARA
  Simulation of transmutation and decay in nuclear systems
  ☆31Updated this week
• cea-trust-platform / TrioCFD-code
  TrioCFD is the Computational Fluid Dynamics (CFD) code based on the TRUST platform. The code contains Front_Tracking, Radiation, ALE for …
  ☆44Updated last week
• LLNL / spheral
  ☆70Updated last week
• PHASTA / phasta
  Parallel Hierarchic Adaptive Stabilized Transient Analysis of compressible and incompressible Navier Stokes equations
  ☆72Updated last year
• NCSU-NCSG / THOR
  THOR is a radiation transport code for unstructured meshes.
  ☆16Updated last year
• cea-trust-platform / trust-code
  TRUST is a thermohydraulic software package for CFD simulations. It was originally designed for incompressible single-phase and Low Mach …
  ☆59Updated last week
• ORNL-CEES / DataTransferKit
  A library for multiphysics solution transfer. ARCHIVED
  ☆50Updated last year
• ezsolti / RFP
  ☆32Updated 3 months ago
• fusion-energy / neutronics-workshop
  A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…
  ☆164Updated last month
• AMReX-Fluids / IAMR
  A parallel, adaptive mesh refinement (AMR) code that solves the variable-density incompressible Navier-Stokes equations.
  ☆95Updated 9 months ago