CEMeNT-PSAAP / MCDC
MC/DC: Monte Carlo Dynamic Code
☆41Updated 3 weeks ago
Alternatives and similar repositories for MCDC
Users that are interested in MCDC are comparing it to the libraries listed below
Sorting:
- THOR is a radiation transport code for unstructured meshes.☆14Updated 8 months ago
- Collection of scripts for managing data for OpenMC☆31Updated 4 months ago
- Simulation of transmutation and decay in nuclear systems☆28Updated 4 months ago
- Stochastic Calculator Of Neutron transport Equation☆43Updated last week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- Repository for Moltres, a code for simulating Molten Salt Reactors☆68Updated last week
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 7 months ago
- Papillon Nuclear Data Library☆16Updated 8 months ago
- Collection of validation scripts, notebooks, results☆11Updated last year
- Workflow and Template Toolkit for Simulation (WATTS)☆30Updated last week
- Sampling nuclear data and uncertainty☆51Updated last week
- open-source Sn software☆33Updated this week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- OpenMC Monte Carlo Code☆17Updated 3 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 10 months ago
- Python ENDF Parser☆33Updated 9 months ago
- Native plotting GUI for model design and verification☆57Updated 3 months ago
- List of open source projects related to OpenMC☆24Updated 8 months ago
- ☆22Updated this week
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆33Updated 5 months ago
- A set of radiation transport mini-applications used for performance optimization on HPC systems.☆29Updated 6 years ago
- Parametric 3-D CAD modeling toolset for stellarator fusion devices☆31Updated this week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated last month
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- Format description for ACE nuclear data files☆21Updated 3 years ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated last week
- CGMF nuclear fission fragment de-excitation statistical code☆25Updated last year
- Toolkit for working with ACE-formatted data files☆28Updated 2 weeks ago
- Collection of models for reactor physics benchmarks☆52Updated 7 months ago
- XSPlot - Neutron cross section plotter for isotopes☆14Updated last year