Open AccessOne-step coupled calculations (Serpent-OpenFOAM) for a fuel rod of the IPR-R1 triga reactor
Author(s) -
Tiago Augusto Santiago Vieira,
Rebeca Cabral Gonçalves,
Izabella Cristina de Paiva Machado,
Guilherme Augusto Moura Vidal,
Higor Fabiano Pereira de Castro,
Nataly Lamounier Ribeiro,
Marcos Pais Barroso Filho,
Wilker Gustavo Ferreira Santos,
Daniel Campolina,
Graiciany de Paula Barros,
Vitor Vasconcelos Araújo Silva,
Adimir dos Santos
Publication year - 2021
Publication title -
brazilian journal of radiation sciences
Language(s) - English
Resource type - Journals
ISSN - 2319-0612
DOI - 10.15392/bjrs.v9i2b.1295
Subject(s) - triga , nuclear engineering , thermal hydraulics , neutron transport , computational fluid dynamics , monte carlo method , solver , computer science , materials science , mechanics , physics , engineering , research reactor , nuclear physics , heat transfer , neutron , mathematics , programming language , statistics
In this work, a single step of coupled calculations for a fuel rod of IPR-R1 TRIGA was performed. The used me-thodology allowed to simulate the fuel pin behavior in steady-state mode for different power levels. The aim of this paper is to present a practical approach to perform coupled calculations between neutronic (Monte Carlo) and thermal-hydraulic (CFD) codes. For this purpose, is necessary to evaluate the influence of the water thermal-physical properties temperature variations on keff parameter. Besides that, Serpent Nuclear Code was used for the neutronics evaluation, while OpenFOAM was used for thermal-hydraulics. OpenFOAM si- mula-tions were made by using a modified chtMultiRegionFoam solver, developed to read Serpent output correctly. The neutronic code was used without any modifications. The results shows that this coupled calculations were consistent and that leads to encouraging further methodology development and its use for full core simulation. Also, the results shows good agreement with calculations performed using other version of OpenFOAM and Milonga as neutronic code.