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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility
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Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility

机译:辐照效应的调查导致辐照辅助应力腐蚀裂解敏感性降低

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摘要

While additive manufacturing (AM) is an area of increasing interest to the nuclear industry, there are significant research and development needs prior to successful implementation of additively manufactured components into reactors. AM steel behaves differently than traditional wrought material, as has been observed in numerous mechanical testing studies. The nuclear industry must also understand the material response to irradiation. This work examines the irradiation damage and the irradiation assisted stress corrosion cracking behavior (IASCC) of both proton irradiated AM and wrought 316L steel. For IASCC testing, specimens were strained to 4% plastic strain in a simulated boiling water reactor environment (288 degrees C, 0.2 mu S/cm). Transmission and scanning electron microscopy, confocal microscopy, and X-ray computed tomography were used to examine coupons of the material as well as tensile bars used in the IASCC testing. This work found that the wrought 316L was more susceptible to IASCC than the AM steel, however, some IASCC was observed in the AM steel when tested with the tensile axis parallel to the build direction. Electron microscopy has shown significantly fewer radiation induced voids formed in the AM steel. While the pre-existing pore network in the AM steel may act as a sink to point defects, this is not expected to be the major factor in the reduced swelling observed in the AM steel. The lower density of radiation induced voids was expected to contribute to the IASCC resistance by decreasing the localization of deformation in the irradiated specimens, however, severity of localized deformation in AM steel, measured in dislocation channel spacing and height, was similar or more severe to that found in wrought. The presence of severe cracking in the wrought specimens did not allow for a direct comparison of localized deformation severities between the AM and wrought steel. (C) 2021 Elsevier B.V. All rights reserved.
机译:虽然添加剂制造(AM)是核工业越来越感兴趣的一个领域,但在反应堆中成功实施添加剂制造组件之前,有大量的研发需求。AM钢的行为不同于传统的锻造材料,这已在许多机械试验研究中观察到。核工业还必须了解材料对辐射的反应。本文研究了质子辐照AM和锻造316L钢的辐照损伤和辐照辅助应力腐蚀开裂行为(IASCC)。对于IASCC测试,在模拟沸水反应堆环境(288摄氏度,0.2μS/cm)中,将试样应变至4%塑性应变。透射和扫描电子显微镜、共焦显微镜和X射线计算机断层扫描用于检查材料试样以及IASCC测试中使用的拉伸棒。这项工作发现,锻造316L比AM钢更容易受到IASCC的影响,然而,当拉伸轴平行于构建方向时,AM钢中观察到一些IASCC。电子显微镜显示AM钢中形成的辐射诱导空洞显著减少。虽然AM钢中预先存在的孔隙网络可能会起到点对点缺陷的作用,但这并不是AM钢中观察到的膨胀减少的主要因素。较低的辐射诱导空洞密度预计将通过减少辐照试样中的变形局部化而有助于提高IASCC电阻,然而,在位错通道间距和高度中测量的AM钢中局部化变形的严重程度与锻造试样中的相似或更严重。由于锻造试样中存在严重裂纹,因此无法直接比较AM和锻造钢之间的局部变形严重程度。(c)2021爱思唯尔B.V.保留所有权利。

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