A CFD analysis of blockage length on a partially blocked fuel rod

Autores/as

  • Nikolas Lymberis Scuro Instituto de Pesquisas Energéticas e Nucleares, Avenida Lineu Prestes, 2242, Centro de Engenharia Nuclear, Zip Code 05508-000, São Paulo, SP, Brazil
  • Pedro Ernesto Umbehaun Instituto de Pesquisas Energéticas e Nucleares, Avenida Lineu Prestes, 2242, Centro de Engenharia Nuclear, Zip Code 05508-000, São Paulo, SP, Brazil
  • Edvaldo Angelo Universidade Presbiteriana Mackenzie, Rua da Consolação, 930, Zip Code 01302-907, São Paulo, SP, Brazil
  • Gabriel Angelo Centro Universitário FEI, Avenida Humberto de Alencar Castelo Branco, 3972-B, Zip Code 09850-901, São Bernardo do Campo, SP, Brazil Instituto de Pesquisas Energéticas e Nucleares, Avenida Lineu Prestes, 2242, Centro de Engenharia Nuclear, Zip Code 05508-000, São Paulo, SP, Brazil
  • Delvonei Alves de Andrade Instituto de Pesquisas Energéticas e Nucleares, Avenida Lineu Prestes, 2242, Centro de Engenharia Nuclear, Zip Code 05508-000, São Paulo, SP, Brazil

DOI:

https://doi.org/10.15392/bjrs.v7i2B.437

Palabras clave:

Partially blocked fuel rod, CFD, ANSYS CFX

Resumen

After a loss of coolant accident (LOCA), fuel rods may balloon. The swelling can partially block the flow channel, affecting the coolability during reflood phase. In order to analyze the influence of blockage length, using a radial blockage of 90%, varying just the blockage length, many steady state numerical simulations has been done using Ansys-CFX code to verify thermal-hydraulic properties according to different forced cooled conditions. Temperature peaks are observed on cladding, followed by a temperature drop. A 5x5 fuel assembly, with 9 centered ballooned fuel rod, flow redistribution inside channels can also be captured, indicating an overheating zone. Therefore, this study conclude, for the same boundary conditions, the longer the blockage length originated after LOCA events, the higher are the clad temperatures, indicating the possibility of overheat during transient conditions on reflood.

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Publicado

2019-06-25

Número

Vol. 7 Núm. 2B (Suppl.) (2019)

Sección

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)

Licencia

Derechos de autor 2019 Brazilian Journal of Radiation Sciences (BJRS)

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Cómo citar

A CFD analysis of blockage length on a partially blocked fuel rod. Brazilian Journal of Radiation Sciences (BJRS), Rio de Janeiro, Brazil, v. 7, n. 2B (Suppl.), 2019. DOI: 10.15392/bjrs.v7i2B.437. Disponível em: https://bjrs.org.br/revista/index.php/REVISTA/article/view/437. Acesso em: 17 jul. 2025.