mcnp

There are 5 repositories under mcnp topic.

• lanl / mcnptools

  mcnpmcnp6
  Language:C++ 54

• kbat / mc-tools

  Some Monte Carlo tools

  monte-carloflukaphitsmcnpxmcnppovrayroot-cern
  Language:Python 39

• inr-kit / McCAD-Library

  a CAD to MC geometry conversion tool

  boostcppcmakecpluplusmcnpopencascade
  Language:C++ 35

• openmc-dev / openmc_mcnp_adapter

  Tool for converting MCNP input files to OpenMC classes/XML

  mcnpmonte-carlo-simulationnuclear-engineeringopenmc
  Language:Python 29
• MontePy

  idaholab / MontePy

  MontePy is a Python library (API) to read, edit, and write MCNP input files.

  mcnp6monte-carloneutronicsapiradiation-transportmcnp
  Language:Python 21

• watts-dev / watts

  Workflow and Template Toolkit for Simulation (WATTS)

  pythonsimulationtemplatesnuclear-energymcnpworkflow-automationopenmc
  Language:Python 21

• ukaea / neutronics_material_maker

  A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak

  openmcmcnpfispactmateriallibraryserpent
  Language:Python 18

• fusion-energy / neutronics_material_maker

  A tool for making reproducible materials and standardizing use across several neutronics codes

  neutronsmateriallibrarydatabaseopenmcmcnpserpentfispact
  Language:Python 17

• alexhagen / wig

  a companion for writing MCNP input decks

  pythonpython-2python-2-7mcnpmonte-carlosimulation
  Language:Python 11

• danyalturkoglu / MCNP-syntax-highlighting

  Syntax highlighting for MCNP input files

  mcnpmcnpx
  9

• IAEA-NDS / ACEMAKER

  A code package to produce ACE-formatted files for MCNP calculations.

  acemcnpnuclear-data
  Language:Fortran 9

• arekfu / t4_geom_convert

  Tool to convert MCNP geometries into TRIPOLI-4 geometries.

  mcnpmcnpxtripoli-4geometryconverter
  Language:Python 6

• ENEA-Fusion-Neutronics / MCNP-Input-Reader

  The package for reading mcnp input in a pythonic way

  mcnpneutronicsradiationnuclear-engineering
  Language:Python 6

• MC-kit / mckit

  Tools to work with MCNP models and results

  mcnpmeshtallytallyradiation-physicsnuclear-engineering
  Language:Jupyter Notebook 5

• repositony / meshtal

  A small suite of tools for interacting with mcnp meshtally files. Supports all common output mesh formats, along with a few uncommon.

  mcnpmeshmeshtallymonte-carlo-simulationrustvtk
  Language:Rust 4

• repositony / vscode_mcnp

  MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.

  mcnpmcnp6radiation-transportsnippetssyntax-highlightingvscode-extension
  4

• travleev / numjuggler

  Tool to rename cells, surfaces, materials and universes in MCNP input files.

  mcnpiterrenumberingpython
  Language:Python 4

• ZXG818 / CylinderMeshingTool

  A high-fidelity, free user input cylinder meshing tool for MCNP.

  couplingmcnpneutronicsthermal-hydraulicudf
  Language:C 3

• mark-fortuna / MCNP-tally-table

  Tally table is a simple GUI program which extracts user defined tallies from a MCNP output.

  mcnpnuclear-engineeringnuclear-fusionnuclear-reactor
  Language:Python 2

• MC-kit / map-stp

  Transfer meta information on cells from an STP file to MCNP model. Set materials and densities according to tags specified in STP model tree.

  mcnpstp
  Language:Python 2

• patrickpark910 / critloadexp

  Python-automated MCNP simulation of the critical loading experiment for a TRIGA Mk.I reactor

  mcnppythonfortran
  Language:Assembly 2

• dvp2015 / TokamakNeutronSource.jl

  Methods to compute neutron source for a given plasma equilibrium state presented with EQDSK file

  mcnpneutronopenmcplasma
  Language:Julia 1

• hungbt1908 / MCNP6-HPGE_Detector_Simulation

  hpgemcnpmonte-carlo-simulation
  Language:Assembly 1

• MCNP-Devel / MCNP-Gists

  Gists to aid in MCNP simulation and analysis

  mcnpparticle-physicsnuclear-physicsmonte-carlo
  Language:Jupyter Notebook 1

• megatharun / MCNP-data-reduction-tool

  A python library to allow ease of data reduction and data viewing for MCNP output file

  mcnpnuclear-engineeringnuclear-physicspython
  Language:Python 1

• niess / gdnp

  Convert a GDML geometry to an MCNP card

  gdmlmcnpconverter
  Language:Python 1

• notxesnayr / sub-channel

  Thermal Hydraulic Sub-Channel Code for an Average Rod (Using MCNP for input values)

  thermodynamicsthermal-conductivitythermalnuclearnumpypythonmcnppressurepeakchfspydermatplotlibpysteam
  Language:Python 1

• repositony / ntools

  A modular toolkit of fast and reliable libraries for neutronics analysis. Several command line tools are built with this core collection of crates.

  monte-carlo-simulationneutronicsrustscientificmcnp
  Language:Rust 1

• ikarino / mcnp_input_generator

  an unofficial MCNP input file generator

  mcnpmcnp6python
  Language:Python 0

• mark-fortuna / radmatcolor

  Recolor your radiant inputs for MCNP model renders.

  mcnprendering
  Language:Python 0

• patrickpark910 / rodcal-mcnp

  Python-automated MCNP simulation of control rod calibration, with integral and differential worth curve calculations, for a TRIGA Mk.I reactor

  pythonmcnpnuclear
  Language:Assembly 0

• repositony / mesh2vtk

  Command line tool to convert MCNP mesh tallies to Visual ToolKit (VTK) formats. Supports all MCNPv6.2 legacy meshtal output formats, for both for rectangular and cylindrical meshes.

  mcnpmeshmeshtallyneutronicsvtk
  Language:Rust 0

• repositony / splitmesh

  Command line tool to split meshtal results into individual files. This is extremely simple but nice to have when needed.

  command-linemcnpmeshtally
  Language:Rust 0

• Funz / plugin-MCNP

  MCNP particle transport code plugin for Funz

  funzmcnpmcnpx
  Language:Batchfile

• MCNP-Devel / Test

  Very drafts

  mcnpmonte-carloscripts