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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Characterization of ion irradiated microstructure and cavity swelling evolution up to high doses in austenitic stainless steels representative of PWR internals
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Characterization of ion irradiated microstructure and cavity swelling evolution up to high doses in austenitic stainless steels representative of PWR internals

机译:奥氏体不锈钢高剂量的离子照射微观结构和空腔肿胀演化的特征

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摘要

Ion irradiations have been performed at 450 degrees C on 304 and 304L austenitic stainless steels representative of PWR internals structure up to high doses (close to 100 dpa). TEM and APT have been carried out on irradiated samples. Depending on the dose, Frank loops, dislocation network, cavities, precipitates and segregations have been observed in both 304 steels grades. Their evolution with dose, and in particular for cavities and corresponding swelling, is described and potential microstructural differences between materials are highlighted. It appears that swelling is limited even up to high doses in both materials due to only slight evolution of cavity density and size from intermediate to high doses. As the irradiation temperature has been chosen to simulate PWR microstructure taking into account a temperature/flux shift effect, the microstructural results are discussed and compared with those of PWR. (C) 2019 Elsevier B.V. All rights reserved.
机译:在304和304L奥氏体不锈钢上以450℃进行离子照射,其代表PWR内部结构,高于高剂量(接近100dPa)。 在辐照样品上进行了TEM和APT。 根据剂量,弗兰克回路,位错网络,腔,沉淀物和偏析,在304型钢等两种等级中都观察到。 描述了它们的剂量,特别是对于空腔和相应的肿胀,并突出显示材料之间的潜在微观结构差异。 由于只有腔密度和尺寸从中间体至高剂量的尺寸轻微演变,肿胀似乎甚至高于两种材料的高剂量。 由于选择了照射温度来模拟PWR微观结构考虑到温度/通量换档效果,讨论了微观结构结果并与PWR的施加相比。 (c)2019 Elsevier B.v.保留所有权利。

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