AlanFord / ZapMeNotLinks
Python library for simple point-kernel photon shielding analyses
☆13Updated 3 weeks ago
Alternatives and similar repositories for ZapMeNot
Users that are interested in ZapMeNot are comparing it to the libraries listed below
Sorting:
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆40Updated last month
- MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks as a placeholder for the full LSP is im…☆14Updated last year
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆42Updated 11 months ago
- List of open source projects related to OpenMC☆30Updated 6 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated last month
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆21Updated 4 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆50Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆81Updated last month
- Nuclear data processing with legacy NJOY☆120Updated 3 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated last week
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 6 months ago
- NJOY for the 21st Century☆84Updated last year
- ☆32Updated 4 months ago
- Tools to translate between different CSG geometry types☆40Updated 6 months ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Native plotting GUI for model design and verification☆64Updated last month
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 2 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last week
- Stochastic Calculator Of Neutron transport Equation☆52Updated last month
- Catalogs a plethora of reactor inputs for OpenMC☆33Updated 9 months ago
- Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/☆13Updated 6 years ago
- Neutronics, Thermal-hydraulics and Structure Multi-physics Coupled Simulation of Heat Pipe Reactor☆12Updated 5 years ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Python ENDF Parser☆39Updated last month
- Collection of scripts for managing data for OpenMC☆38Updated 2 weeks ago
- Sampling nuclear data and uncertainty☆53Updated last month
- OpenMC Monte Carlo Code☆23Updated 10 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 months ago