Simulation of Mechanical Behavior of Fuel Pellets With Different Geometries
DOI:
https://doi.org/10.15392/bjrs.v7i2B.398Keywords:
geometry pellet, FRAPCON code, ANSYS softwareAbstract
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.
Downloads
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.
Downloads
Published
Issue
Section
License
Copyright (c) 2019 Brazilian Journal of Radiation Sciences
This work is licensed under a Creative Commons Attribution 4.0 International License.
Licensing: The BJRS articles are licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons license, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons license and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/