One-step coupled calculations (Serpent-OpenFOAM) for a fuel rod of the IPR-R1 triga reactor

Authors

  • Tiago Augusto Santiago Vieira Nuclear Technology Development Center (CDTN)
  • Rebeca Cabral Gonçalves Nuclear Technology Development Center (CDTN)
  • Izabella Cristina de Paiva Machado Nuclear Technology Development Center (CDTN)
  • Guilherme Augusto Moura Vidal Nuclear Technology Development Center (CDTN)
  • Higor Fabiano Pereira Castro Universidade Federal de Minas Gerais https://orcid.org/0000-0003-3822-0546
  • Nataly Lamounier Ribeiro Universidade Federal de Minas Gerais - UFMG
  • Marcos Pais Barroso Filho Nuclear Technology Development Center (CDTN)
  • Wilker Gustavo Ferreira Santos Nuclear Technology Development Center (CDTN)
  • Daniel de Almeida Magalhães Campolina Nuclear Technology Development Center (CDTN)
  • Graiciany de Paula barros Nuclear Technology Development Center (CDTN)
  • Vitor Vasconcelos Araújo Silva Nuclear Technology Development Center (CDTN)
  • André Augusto Campagnole dos Santos Nuclear Technology Development Center (CDTN)

DOI:

https://doi.org/10.15392/bjrs.v9i2B.1295

Keywords:

Monte Carlo, CFD, Multi-physics, Serpent, OpenFOAM.

Abstract

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.

Downloads

Download data is not yet available.

Author Biographies

Tiago Augusto Santiago Vieira, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

Rebeca Cabral Gonçalves, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

Izabella Cristina de Paiva Machado, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

Guilherme Augusto Moura Vidal, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

Higor Fabiano Pereira Castro, Universidade Federal de Minas Gerais

Department of Nuclear Engineering

Nataly Lamounier Ribeiro, Universidade Federal de Minas Gerais - UFMG

Department of Mechanical Engineering

Marcos Pais Barroso Filho, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

Wilker Gustavo Ferreira Santos, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

Daniel de Almeida Magalhães Campolina, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

Graiciany de Paula barros, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

Vitor Vasconcelos Araújo Silva, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

André Augusto Campagnole dos Santos, Nuclear Technology Development Center (CDTN)

Thermal-Hydraulic and Neutronics Laboratory - LTHN

References

“Coupling Serpent and OpenFOAM for neutronics CFD multi-physics calculations”, https://aaltodoc.aalto.fi/bitstream/handle/123456789/17759/ mas-ter_Tuominen_Riku_2015.pdf?sequence=1&isAllowed=y, (2019).

LEPPANEN, J. et al “The Serpent Monte Carlo code: Status, development and applications in 2013.”, Annals of Nuclear Energy, 82, pp. 142–150, (2015).

“OpenFOAM: User Guide version 6”, http://foam.sourceforge.net/docs/Guides-a4/OpenFOAMUserGuide-A4.pdf , (2018).

IVANOV, K.; AVRAMOVA, M. “Challenges in coupled thermal–hydraulics and neutron-ics simulations for LWR safety analysis”, Annals of Nuclear Energy, 34, pp. 501–513, (2007).

FERRARO, D. et al, “A multi-physics analysis for the actuation of the SSS in Opal reactor”, Nuclear Sciences & Technologies, 4, pp. 8, (2018).

TUOMINEN, R.; VALTAVIRTA, V.; and LEPPANEN, J. “Application of the Serpent- OpenFOAM coupled code system to the SEALER reactor core”, Physor, Mexico, april, (2018).

MARTIN, W. “Challenges and prospects for whole-core Monte Carlo analysis”, Nuclear Engineering and Technology, 44, (2012).

VASCONCELOS, V. et al “Coupled unstructured fine-mesh neutronics and thermal–hydraulics methodology using open software: A proof-of-concept”, Annals of Nuclear En-ergy, 115, pp. 173–185, (2018).

“Acoplamento neutrônico e termo-hidráulico usando os códigos milonga e Open- FOAM: uma abordagem com software livre”,

http://www.repositorio.cdtn.br:8080/jspui/bitstream/123456789/1220/1/ Tese%20Vitor%20Vasconcelos.pdf, (2016).

GEUZAINE, C. and REMACLE, J. F. “Gmsh: a three-dimensional finite element mesh generator withbuilt-in pre-and post-processing facilities”, International Journal for Numerical Methods in Engineering, 0, pp. 1–24, (2009).

Downloads

Published

2021-07-25

How to Cite

Vieira, T. A. S., Gonçalves, R. C., Machado, I. C. de P., Vidal, G. A. M., Castro, H. F. P., Ribeiro, N. L., Filho, M. P. B., Santos, W. G. F., Campolina, D. de A. M., barros, G. de P., Silva, V. V. A., & dos Santos, A. A. C. (2021). One-step coupled calculations (Serpent-OpenFOAM) for a fuel rod of the IPR-R1 triga reactor. Brazilian Journal of Radiation Sciences, 9(2B (Suppl.). https://doi.org/10.15392/bjrs.v9i2B.1295

Issue

Section

XXI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XXI ENFIR) and VI ENIN

Most read articles by the same author(s)