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Damage tolerance of nuclear graphite at elevated temperatures

机译:高温下核石墨的损伤容限

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摘要

Nuclear-grade graphite is a critically important high-temperature structural material for current and potentially next generation of fission reactors worldwide. It is imperative to understand its damage-tolerant behaviour and to discern the mechanisms of damage evolution under in-service conditions. Here we perform in situ mechanical testing with synchrotron X-ray computed micro-tomography at temperatures between ambient and 1,000 °C on a nuclear-grade Gilsocarbon graphite. We find that both the strength and fracture toughness of this graphite are improved at elevated temperature. Whereas this behaviour is consistent with observations of the closure of microcracks formed parallel to the covalent-sp2-bonded graphene layers at higher temperatures, which accommodate the more than tenfold larger thermal expansion perpendicular to these layers, we attribute the elevation in strength and toughness primarily to changes in the residual stress state at 800–1,000 °C, specifically to the reduction in significant levels of residual tensile stresses in the graphite that are ‘frozen-in’ following processing.
机译:核级石墨是全球目前和潜在的下一代裂变反应堆的至关重要的高温结构材料。当务之急是要了解其损伤容忍行为,并辨别在役条件下损伤演变的机制。在这里,我们在环境温度和1,000°C之间的温度下,在核级Gilsocarbon石墨上用同步加速器X射线计算机断层扫描进行原位机械测试。我们发现,该石墨的强度和断裂韧性在高温下均得到改善。尽管这种行为与在较高温度下观察到的平行于共价键-sp 2 -键合的石墨烯层平行形成的微裂纹的闭合相符,但这些裂纹垂直于这些层的热膨胀大于十倍。归因于强度和韧性的提高主要归因于800–1,000 C时残余应力状态的变化,特别是由于石墨中加工后“冻结”的残余拉伸应力的显着降低。

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