使用Mini-CT试样对辐照前后低架子Linde 80焊缝的断裂韧性进行表征

M. Sokolov
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引用次数: 5

摘要

在反应堆压力容器(RPV)领域,使用主曲线方法直接测量过渡区域的断裂韧性,Mini-CT试样正成为一种非常流行的几何形状。在本研究中,Mini-CT试样是由先前测试的Midland低上架子Linde 80焊缝的Charpy试样在未辐照和辐照条件下加工而成的。辐照标本已被定性为ORNL-EPRI-CRIEPI联合合作计划的一部分。之所以选择Linde 80焊缝,是因为它已经通过常规试样在辐照条件下进行了广泛的表征,并且因为需要验证Mini-CT试样对低上层材料的应用-对于一些老一代rpv的辐照材料来说,这种情况更有可能发生。结果表明,从这些Mini-CT样品中得到的断裂韧性参考温度To与之前记录的该材料在未辐照和辐照条件下的To值很好地一致。然而,这项研究表明,在实际操作中,使用比ASTM E1921规定的最小数量大得多的样品是非常可取的。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Use of Mini-CT Specimens for Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld Before and After Irradiation
Mini-CT specimens are becoming a highly popular geometry for use in reactor pressure vessel (RPV) community for direct measurement of fracture toughness in the transition region using the Master Curve methodology. In the present study, Mini-CT specimens were machined from previously tested Charpy specimens of the Midland low upper-shelf Linde 80 weld in both, unirradiated and irradiated conditions. The irradiated specimens have been characterized as part of a joint ORNL-EPRI-CRIEPI collaborative program. The Linde 80 weld was selected because it has been extensively characterized in the irradiated condition by conventional specimens, and because of the need to validate application of Mini-CT specimens for low upper-shelf materials — a more likely case for some irradiated materials of older generation RPVs. It is shown that the fracture toughness reference temperatures, To, derived from these Mini-CT specimens are in good agreement with To values previously recorded for this material in the unirradiated and irradiated conditions. However, this study indicates that in real practice it is highly advisable to use a much larger number of specimens than the minimum number prescribed in ASTM E1921.
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