mohamedlahdour / OpenNTP
In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.
☆11Updated 4 years ago
Alternatives and similar repositories for OpenNTP:
Users that are interested in OpenNTP are comparing it to the libraries listed below
- Neutronics, Thermal-hydraulics and Structure Multi-physics Coupled Simulation of Heat Pipe Reactor☆10Updated 5 years ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated 2 years ago
- OpenMC wrapped as a Moose App☆16Updated last year
- ☆30Updated 2 months ago
- Stochastic Calculator Of Neutron transport Equation☆42Updated last week
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 8 months ago
- open-source Sn software☆29Updated this week
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆26Updated 3 years ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆53Updated this week
- List of open source projects related to OpenMC☆25Updated 7 months ago
- OpenMC中文教程 ( 如何编译、安装、使用OpenMC教程 )☆40Updated 3 years ago
- ☆21Updated 2 weeks ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 10 months ago
- Python ENDF Parser☆33Updated 8 months ago
- Native plotting GUI for model design and verification☆57Updated 3 months ago
- Machine learning and artificial intelligence benchmarking library for nuclear engineering applications.☆28Updated last month
- Convert OpenMC Geometry Components to CAD☆17Updated 5 months ago
- Collection of models for reactor physics benchmarks☆52Updated 6 months ago
- 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
- Nuclear data processing with legacy NJOY☆106Updated last week
- Workflow and Template Toolkit for Simulation (WATTS)☆30Updated last week
- Collection of scripts for managing data for OpenMC☆31Updated 3 months ago
- Vim plugin for MOOSE Framework input file format☆12Updated last year
- curated documents pertaining to early molten salt reactor research.☆22Updated last year
- Tool for converting MCNP input files to OpenMC classes/XML☆40Updated 2 months ago
- API for parsing and post-processing many MC simulations related files☆15Updated 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 4 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated last week