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Evaluation of stress corrosion cracking of irradiated 304L stainless steel in PWR environment using heavy ion irradiation

机译:重离子辐照在压水反应堆环境下辐照304L不锈钢的应力腐蚀开裂评估

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摘要

IASCC has been a major concern regarding the structural and functional integrity of core internals of PWR's, especially baffle-to-former bolts. Despite numerous studies over the past few decades, additional evaluation of the parameters influencing IASCC is still needed for an accurate understanding and modeling of this phenomenon. In this study, Fe irradiation at 450 degrees C was used to study the cracking susceptibility of 304 L austenitic stainless steel. After 10 MeV Fe irradiation to 5 dpa, irradiation-induced damage in the microstructure was characterized and quantified along with nano-hardness measurements. After 4% plastic strain in a PWR environment, quantitative information on the degree of strain localization, as determined by slip-line spacing, was obtained using SEM. Fe-irradiated material strained to 4% in a PWR environment exhibited crack initiation sites that were similar to those that occur in neutron-and proton-irradiated materials, which suggests that Fe irradiation may be a representative means for studying IASCC susceptibility. Fe-irradiated material subjected to 4% plastic strain in an inert argon environment did not exhibit any cracking, which suggests that localized deformation is not in itself sufficient for initiating cracking for the irradiation conditions used in this study. (C) 2016 Elsevier B.V. All rights reserved.
机译:对于压水堆的核心内部结构和功能的完整性,IASCC一直是一个主要关注点,尤其是挡板到前者的螺栓。尽管在过去的几十年中进行了大量研究,但仍需要对影响IASCC的参数进行额外评估,以准确理解和建模此现象。在这项研究中,Fe在450℃下的辐照被用来研究304 L奥氏体不锈钢的开裂敏感性。在10 MeV Fe辐照至5 dpa后,对辐照引起的微观结构损伤进行了表征,并进行了纳米硬度测量。在压水堆环境中发生4%的塑性应变后,使用SEM获得有关滑移线间距确定的应变局部化程度的定量信息。在PWR环境中应变至4%的铁辐照材料的裂纹萌生点与中子和质子辐照材料中出现的裂纹相似,这表明铁辐照可能是研究IASCC磁化率的代表性方法。在惰性氩气环境中受铁辐照的材料在4%的塑性应变下没有表现出任何开裂,这表明在本研究中使用的辐照条件下,局部变形本身不足以引发开裂。 (C)2016 Elsevier B.V.保留所有权利。

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