Revanth Mattey , Alexander Swearingen , Hakan Ozaltun , Jeffrey J. Giglio
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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 AA 6061 cladding during this transient process of HIP. The present study focuses on developing a computational model that predicts the creep behavior of the aluminum cladding in the fuel plates during the HIP process, 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. 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引用次数: 0
摘要
采用热等静压(HIP)技术制造了由高密度低浓缩铀(LEU) u - 10mo基燃料箔封装在铝合金(AA)包层中的板型燃料元件。在HIP过程中,燃料板系统被加热到560°C,然后冷却到室温。这种热循环对铝包层的力学性能有显著影响,实验研究表明,经过hip焊后,铝包层的力学性能由AA 6061-T6的力学性能转变为更接近O回火的力学性能。更具体地说,包层的极限强度降低,而其延展性增加,这使得捕捉机械行为和材料性能的变化变得具有挑战性。了解HIP过程中产生的残余应力对于评估燃料板在各种温度、压力和辐照下的完整性至关重要。为了模拟HIP键合过程,假设熔覆层的弹性、塑性和热性能与AA 6061-O回火相似。然而,主要的挑战在于缺乏可用的数据,以建立在此瞬变过程中AA 6061包层的蠕变模型。本研究的重点是建立一个计算模型,预测燃料板中铝包层在HIP制造过程中的蠕变行为,因为包层蠕变显著影响U-10Mo燃料板在HIP制造过程中产生的残余应力。此外,由于HIP键合发生在接近铝熔点的高温下,因此本研究考虑的是温度依赖的arrhenius型蠕变模型。特别地,采用双曲正弦蠕变模型来估计预制铝包层的蠕变性能。使用新标定的蠕变模型预测的U-10Mo燃料残余应力与实验测量结果吻合较好,验证了模型的准确性。
Development of a thermal creep model for aluminum alloy 6061 cladding in U-10Mo monolithic fuel plates
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 °C, 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 AA 6061 cladding during this transient process of HIP. The present study focuses on developing a computational model that predicts the creep behavior of the aluminum cladding in the fuel plates during the HIP process, 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.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.