首页> 外文期刊>Journal of Korean Institute of Metal and Materials >Evaluation of Temper Embrittlement Effect and Segregation Behaviors on Ni-Mo-Cr High Strength Low Alloy RPV Steels with Changing P and Mn Contents
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Evaluation of Temper Embrittlement Effect and Segregation Behaviors on Ni-Mo-Cr High Strength Low Alloy RPV Steels with Changing P and Mn Contents

机译:P和Mn含量变化的Ni-Mo-Cr高强度低合金RPV钢的回火脆化效果和偏析行为的评价

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Higher strength and fracture toughness of reactor pressure vessel steels can be obtained by changing the material specification from that of Mn-Mo-Ni low alloy steel (SA508 Gr.3) to Ni-Mo-Cr low alloy steel (SA508 Gr.4N). However, the operation temperature of the reactor pressure vessel is more than 300°C and the reactor operates for over 40 years. Therefore, we need to have phase stability in the high temperature range in order to apply the SA508 Gr.4N low alloy steel for a reactor pressure vessel. It is very important to evaluate the temper embrittlement phenomena of SA508 Gr.4N for an RPV application. In this study, we have performed a Charpy impact test and tensile test of SA508 Gr.4N low alloy steel with changing impurity element contents such as Mn and P. And also, the mechanical properties of these low alloy steels after long-term heat treatment (450 °C, 2000hr) are evaluated. Further, evaluation of the temper embrittlement by fracture analysis was carried out. Temper embrittlement occurs in KL4-Ref and KL4-P, which show a decrease of the elongation and a shifting of the transition curve toward high temperature. The reason for the temper embrittlement is the grain boundary segregation of the impurity element P and the alloying element Ni. However, KL4-Ref shows temper embrittlement phenomena despite the same contents of P and Ni compared with SC-KL4. This result may be caused by the Mn contents. In addition, the behavior of embrittlement is not largely affected by the formation of M_3P phosphide or the coarsening of Cr carbides.
机译:通过将材料规格从Mn-Mo-Ni低合金钢(SA508 Gr.3)更改为Ni-Mo-Cr低合金钢(SA508 Gr.4N),可以获得更高的反应堆压力容器钢的强度和断裂韧性。 。但是,反应堆压力容器的工作温度超过300℃,并且反应堆工作了40多年。因此,为了将SA508 Gr.4N低合金钢用于反应堆压力容器,我们需要在高温范围内具有相稳定性。对于RPV应用,评估SA508 Gr.4N的回火脆化现象非常重要。在这项研究中,我们对改变杂质元素含量(例如Mn和P)的SA508 Gr.4N低合金钢进行了夏比冲击试验和拉伸试验。此外,这些低合金钢经过长期热处理后的力学性能评价(450℃,2000hr)。此外,通过断裂分析进行了回火脆化的评价。回火脆化发生在KL4-Ref和KL4-P中,它们显示出伸长率的降低和过渡曲线向高温的移动。回火脆化的原因是杂质元素P和合金元素Ni的晶界偏析。但是,与SC-KL4相比,尽管P和Ni的含量相同,但KL4-Ref仍显示出回火脆化现象。该结果可能是由Mn含量引起的。此外,脆化行为不受M_3P磷化物的形成或Cr碳化物粗化的影响很大。

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