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Characterization of transition behavior in SA508 Gr.4N Ni-Cr-Mo low alloy steels with microstructural alteration by Ni and Cr contents

机译:镍和铬含量对SA508 Gr.4N Ni-Cr-Mo低合金钢显微组织变化的过渡行为表征

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摘要

SA508 Gr.4N Ni-Cr-Mo low alloy steel, in which Ni and Cr contents are higher than in commercial reactor pressure vessel (RPV) steels, may be a candidate RPV material with the improved strength and toughness due to its tempered martensitic microstructure. This study aims at assessing the effects of microstructural factors with alloying element contents on the transition properties of Ni-Cr-Mo low alloy steels. Model alloys with different Ni and Cr contents were fabricated and their Charpy impact toughness and fracture toughness were examined in the transition region according to ASTM E23 and El 921 standard procedures, respectively. The test results showed extensive improvements of both impact toughness and fracture toughness with increasing Ni and Cr contents. However, Ni content was more effective on the impact toughness than on the fracture toughness, while Cr content was more effective on the fracture toughness. In order to identify a difference in effects of alloying elements contents on the fracture toughness and impact toughness, the relations between the transition properties and the scale of the microstructural features such as packets and carbides are discussed in detail.
机译:SA508 Gr.4N Ni-Cr-Mo低合金钢中的Ni和Cr含量高于商用反应堆压力容器(RPV)钢,由于其回火的马氏体显微组织,具有改善的强度和韧性可能是候选的RPV材料。这项研究旨在评估含合金元素含量的微结构因素对Ni-Cr-Mo低合金钢的过渡性能的影响。制备了具有不同Ni和Cr含量的模型合金,并根据ASTM E23和El 921标准程序分别在过渡区域中检查了其夏比冲击韧性和断裂韧性。试验结果表明,随着镍和铬含量的增加,冲击韧性和断裂韧性均得到了很大的提高。但是,Ni含量对冲击韧性比断裂韧性更有效,而Cr含量对断裂韧性更有效。为了确定合金元素含量对断裂韧性和冲击韧性的影响之间的差异,详细讨论了过渡性能与微观结构特征(例如小包和碳化物)的尺度之间的关系。

著录项

  • 来源
    《Materials Science and Engineering》 |2011年第2011期|p.156-163|共8页
  • 作者单位

    Department of Materials Science and Engineering, KAIST, Daejeon 305-701, Republic of Korea,Nuclear Materials Research Division, KAER1, Daejeon 305-353, Republic of Korea;

    Department of Materials Science and Engineering, KAIST, Daejeon 305-701, Republic of Korea,Nuclear Materials Research Division, KAER1, Daejeon 305-353, Republic of Korea;

    Nuclear Materials Research Division, KAER1, Daejeon 305-353, Republic of Korea;

    Nuclear Materials Research Division, KAER1, Daejeon 305-353, Republic of Korea;

    Department of Materials Science and Engineering, KAIST, Daejeon 305-701, Republic of Korea;

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  • 正文语种 eng
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  • 关键词

    transition property toughness low alloy steel reactor pressure vessel;

    机译:转变性能韧性低合金钢反应堆压力容器;

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