OFELIA: Openmc-FEnicsx for muLtiphysics tutorIAl Authors: Lorenzo Loi, Stefano Riva, Carolina Introini, Antonio Cammi
This repository collects the supporting code for OFELIA (Openmc-FEnicsx for muLtiphysics tutorIAl): an open-source tool to simulate multi-physics nuclear cases adopting OpenMC (v 0.13.2) and FEniCSx (v. 0.6.0) for Python. Moreover, useful tutorials are available for the single-physics codes OpenMC and FEniCSx.
The aim of this repository consists in collecting tutorials for FEniCSx and OpenMC, and their coupling version (OFELIA), specific to nuclear reactors applications. In particular, the former FEniCSx collects the following:
- Fluid Dynamics: cavity, backward facing step and laminar flow over cylinder.
- Neutronics (MultiGroup Diffusion): ANL benchmarks and MultiPhysics application
whereas, the OpenMC tutorial implements the simulation of a TRIGA reactor.
If you use this set of codes in your research, please cite the following paper
- L. Loi, S. Riva, C. Introini, F. Giacobbo, X. Wang, and A. Cammi, “OFELIA: An OpenMC-FEniCSx coupling for neutronic calculation with temperature feedback,” Nuclear Engineering and Design, vol. 428, p. 113480, 2024.
Here reported in .bib format
@article{LOI2024113480,
title = {OFELIA: An OpenMC-FEniCSx coupling for neutronic calculation with temperature feedback},
journal = {Nuclear Engineering and Design},
volume = {428},
pages = {113480},
year = {2024},
issn = {0029-5493},
doi = {https://doi.org/10.1016/j.nucengdes.2024.113480},
url = {https://www.sciencedirect.com/science/article/pii/S0029549324005806},
author = {Lorenzo Loi and Stefano Riva and Carolina Introini and Francesca Giacobbo and Xiang Wang and Antonio Cammi},
keywords = {OpenMC, FEniCSx, Nuclear reactor, Monte Carlo, Thermal hydraulics},
}If interested, contact [email protected] or [email protected]