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Microstructural and Fractographic Characterization of a Thermally Embrittled Nuclear Grade Steel: Part I - Annealing

机译:热脆核级钢的显微组织和断裂形貌表征:第一部分-退火

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摘要

A nuclear reactor pressure vessel steel was submitted to different annealing heat treatments aimed at simulating neutron irradiation damage. The obtained microstructures were mechanically tested with subsequent metallographic and fractographic characterization. The relevant microstructural and fractographic aspects were employed in the interpretation of the mechanical behavior of the microstructures in both quasi-static (J-R curve) and dynamic (Charpy impact) loading regimes. A well defined relationship was determined between the elastic-plastic fracture toughness parameter J-integral and the Charpy impact energy for very most of the microstructures.
机译:核反应堆压力容器钢接受了旨在模拟中子辐照损伤的不同退火热处理。对获得的微结构进行机械测试,随后进行金相和分形表征。在准静态(J-R曲线)和动态(夏比冲击)加载方式下,在解释微观结构的力学行为时采用了相关的微观结构和分形学方面。对于大多数微观结构,在弹塑性断裂韧性参数J积分和夏比冲击能之间确定了明确定义的关系。

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