Simulation of Mechanical Behavior of Fuel Pellets With Different Geometries

Authors

  • Amanda Abati Aguiar Navy Technological Center
  • Danilo Faria
  • José Berretta
  • Paulo Afonso Rodi
  • Marcelo Santos
  • Antônio Teixeira e Silva

DOI:

https://doi.org/10.15392/bjrs.v7i2B.398

Keywords:

geometry pellet, FRAPCON code, ANSYS software

Abstract

Typical Pressurized Water Reactors (PWR) fuel rods are manufactured using zirconium-based alloys as cladding and slightly enriched UO2 sintered pellets as fuel. However, in the last years efforts have been made to develop Accident Tolerant Fuels (ATF) focusing mainly in new materials to replace the cladding in order to avoid the exothermic reaction with steam experienced by zirconium-based alloys under accident conditions as observed during the Fukushima Daiichi accident. In this sense, iron-based alloys appear as a possibility to replace conventional zirconium-based alloys, and the effect of the pellet geometry in the performance of iron-based alloys fuel rods shall be investigated. The fuel pellet geometry experiences changes due to irradiation can promote early gap closure, mechanical loadings to the cladding and/or bamboo effects due to the combination of loads and irradiation creep, and all these effects depend also on the cladding properties. The objective of this paper was to address the influence of geometric parameters in the fuel pellet behavior of a stainless steel fuel rod by means of structural mechanical analysis using the well-known ANSYS software. The parameters evaluated in this paper considered fuel pellet with and without chamfer and dish. The data related to the fuel pellet performance under irradiation were obtained using a modified version of the FRAPCON code considering stainless steel as cladding. Results obtained from mechanical evaluation considering the effects through the responses of the axial, radial, plastic deformations, and resulting tensions were evaluated.

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References

“FRAPCON-3.5: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, NUREG/CR-7022, Vol. 1, Rev. 1.

ANSYS, www.ansys.com/products, 2017.

STRASSE, A., et. al. An Evaluation of Stainless Steel Cladding for Use in Current Design LWRS. EPRI – NP--2642, Palo Alto, December, 1982.

ABE. A.; GIOVEDI, C., et.al. Revisiting Stainless Steel as PWR Fuel Rod Cladding after Fukushima Daiichi Accident. Journal of Energy and Power Engineering 8, p. 973-980, 2014.

LUSCHER. W. G., et.al. Material Property Correlations: Comparisons between FRAPCON -3.5, FRAPTRAN-1.5, and MATPRO. NUREG/CR-7024, Rev. 01, 2014.

ALLISON. C. M., et.al. SCDAP / RELAP5/ MOD 3.1. Code Manual Volume IV: MATPRO- A Library of Materials Properties for Light -Water -Reactor Accident Analysis. Nov.,1993.

DONALD. L. H., et. al. MATPRO - Version 11: A Handbook of Materials Properties for use in the Analysis of Light Water Reactor Fuel Rod Behavior. NUREG/CR-0497, 1979.

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Published

2019-06-25

Issue

Section

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

How to Cite

Simulation of Mechanical Behavior of Fuel Pellets With Different Geometries. Brazilian Journal of Radiation Sciences, Rio de Janeiro, Brazil, v. 7, n. 2B (Suppl.), 2019. DOI: 10.15392/bjrs.v7i2B.398. Disponível em: https://bjrs.org.br/revista/index.php/REVISTA/article/view/398.. Acesso em: 24 nov. 2024.

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