paulromano / cnl-workshop
OpenMC Workshop for Canadian Nuclear Laboratories
☆10Updated 8 years ago
Alternatives and similar repositories for cnl-workshop
Users that are interested in cnl-workshop are comparing it to the libraries listed below
Sorting:
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆33Updated last month
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- List of open source projects related to OpenMC☆24Updated 8 months ago
- API for parsing and post-processing many MC simulations related files☆15Updated 3 weeks ago
- curated documents pertaining to early molten salt reactor research.☆22Updated last year
- Example Jupyter notebooks for OpenMC☆37Updated 2 months ago
- Stochastic Calculator Of Neutron transport Equation☆43Updated last week
- ☆22Updated this week
- Tools to translate between different CSG geometry types☆37Updated last year
- ☆30Updated 2 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated last month
- Python ENDF Parser☆33Updated 9 months ago
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 3 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆41Updated 3 months ago
- Native plotting GUI for model design and verification☆57Updated 3 months ago
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- Catalogs a plethora of reactor inputs for OpenMC☆23Updated 2 months ago
- Collection of scripts for managing data for OpenMC☆31Updated 4 months ago
- JADE, a novel nuclear data libraries V&V tool☆27Updated this week
- Convert OpenMC Geometry Components to CAD☆17Updated 5 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆43Updated this week
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆39Updated 5 months ago
- Computational inputs, reference outputs and experimental data for V&V systems☆12Updated last month
- In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.☆11Updated 4 years ago
- ☆78Updated 11 months ago
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 9 months ago
- Nuclear data processing with legacy NJOY☆107Updated last month
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Accelerated Discretized Geometry☆14Updated this week
- open-source Sn software☆33Updated this week