Development of a Thermal Creep Model for Aluminum Alloy 6061 Cladding in U-10Mo Monolithic Fuel Plates
Journal Article
·
· Nuclear Engineering and Design
- Idaho National Laboratory
- U.S. Nuclear Regulatory Commission
Plate-type fuel elements consisting of a high-density, low-enriched uranium (LEU) U–10Mo-based fuel foil encapsulated in an aluminum alloy (AA) cladding are fabricated using the hot isostatic pressing (HIP) technique. During the HIP process, the fuel plate system is heated to 560 degree celsius, then cooled to room temperature. This heat cycle significantly affects the mechanical properties of the aluminum cladding, and experimental investigations have shown that, post-HIP bonding, the mechanical properties of the aluminum cladding transition from those of AA 6061-T6 to something closer to the O temper. More specifically, the ultimate strength of the cladding decreases while its ductility increases, making it challenging to capture the changes in mechanical behavior and material properties. Understanding the residual stresses generated during the HIP process is critical for assessing the fuel plate's integrity under various temperature, pressure, and irradiation. To simulate the HIP bonding process, the elastic, plastic, and thermal properties of the cladding are assumed to be similar to those of AA 6061-O temper. However, the primary challenge lies in the lack of available data for the creep model of the O temper. The present study focuses on developing a computational model that predicts the creep behavior of the post-HIP aluminum cladding in the fuel plates, as cladding creep significantly influences the residual stresses generated in U-10Mo fuel plates during HIP fabrication. Furthermore, as HIP bonding occurs at high temperatures that are nearing the melting point of aluminum, the present work considered a temperature-dependent Arrhenius-type creep model. In particular, a hyperbolic sine creep model is employed to estimate the creep properties of the as-fabricated aluminum cladding. The residual stresses predicted in the U-10Mo fuel when using the newly calibrated creep model closely align with the experimental measurements, validating the model's accuracy.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE); USDOE National Nuclear Security Administration (NNSA)
- Grant/Contract Number:
- AC07-05ID14517
- OSTI ID:
- 3013768
- Report Number(s):
- INL/JOU-24-81458
- Journal Information:
- Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: 15 December 2025 Vol. 445
- Country of Publication:
- United States
- Language:
- English
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