研究高燃耗UO2中微观结构演变的独立效应MiniFuel辐照实验设计

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jacob P. Gorton, Annabelle G. Le Coq, Amber C. Telles, Kara M. Godsey, Jonathan R. Chappell, Christian M. Petrie, Nathan A. Capps
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引用次数: 0

摘要

在轻水反应堆(LWRs)的商业运行过程中,由于局部温度和燃耗的空间变化,UO2燃料球团的微观结构演变在球团半径范围内存在显著差异。将轻水堆换料周期延长至24个月的主要障碍是在冷却剂损失事故(LOCA)中,某些高燃耗燃料微结构对燃料碎片、重新安置和扩散(FFRD)的敏感性。虽然高燃耗结构在球团边缘区域的FFRD已经得到了很好的研究,但在高燃耗商业燃料棒模拟LOCA测试后,在球团中半径附近的第二个区域(称为“暗区”)观察到的细碎裂却鲜为人知。本文描述了设计、分析和执行一个独立效应的MiniFuel辐照实验,旨在确定ffrd敏感暗区微结构形成的特定温度和燃耗制度。小圆盘样品(直径3毫米,厚度约0.3毫米)可以更精确地控制相对均匀的温度和燃耗条件。共制作了42个样品,样品具有典型的低燃耗燃料密度(理论密度的96%-98%)和晶粒尺寸(~ 12 μm),并在高燃耗低燃耗燃料的中半径范围内的温度(600°C - 1000°C)和放电燃烧(50-72 MWd/kg-U)范围内进行辐照。235U浓度相同的燃料样品被插入高通量同位素反应堆的两个辐照位置,目前正在进行辐照,以进一步评估速率效应(裂变速率、温度下的时间)对微观结构演变的影响。本文详细介绍了燃料的制作过程和实验设计所用的热中子模拟。实验的第二个目标是观察不同辐照条件下的裂变气体释放(FGR),这项工作提供了所有燃料样品的FGR的一阶预测。从这些实验中获得的见解将为未来的高燃耗核心设计提供信息,这些设计可以最大限度地减少易感微结构的形成,并最终实现24个月的换料周期,同时最大限度地减少易受FFRD影响的燃料比例。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Design of a separate effects MiniFuel irradiation experiment investigating microstructure evolution in high burnup UO2
The microstructural evolution of UO2 fuel pellets during commercial operation in light water reactors (LWRs) is known to vary significantly across the pellet radius due to spatial variations in local temperature and burnup. The primary obstacle to extending LWR refueling cycles to 24-month intervals is the susceptibility of certain high burnup fuel microstructures to fuel fragmentation, relocation, and dispersal (FFRD) during a loss of coolant accident (LOCA). Although FFRD of the high burnup structure in the rim region of a pellet is well studied, the fine fragmentation that has been observed in a second region, near the midradius of the pellet (termed the “dark zone”) following mock LOCA testing of high burnup commercial fuel rods is less understood. This paper describes the design, analysis, and execution of a separate effects MiniFuel irradiation experiment that aims to identify the specific temperature and burnup regimes under which FFRD-susceptible dark zone microstructures form. The small disc specimens (3 mm diameter by ∼0.3 mm thick) enable more precise control of the relatively uniform temperature and burnup conditions. A total of 42 specimens were fabricated with typical LWR fuel densities (∼96%–98% of theoretical density) and grain sizes (∼12 μm) and are being irradiated over a range of temperatures (600°C–1000°C) and discharge burnups (50–72 MWd/kg-U) that bound the midradius region of high burnup LWR fuel. Fuel specimens with identical 235U enrichments were inserted in two irradiation locations in the High Flux Isotope Reactor and are currently undergoing irradiation to further evaluate the impact of rate effects (fission rate, time at temperature) on the microstructural evolution. The fuel fabrication and the thermal and neutronic simulations used for designing the experiment are detailed in this paper. A secondary objective of the experiment is to observe fission gas release (FGR) under the various irradiation conditions, and this work provides first-order predictions of FGR from all fuel specimens. The insights gained from these experiments will inform future high burnup core designs that could minimize the formation of susceptible microstructures and ultimately enable 24-month refueling cycles while minimizing the fraction of the fuel susceptible to FFRD.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
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.
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