Effects of Cr Carbides Formation on the High Temperature Creep Property of Alloy 690 for Steam Generator Tube Material

IF 1.1 4区 材料科学 Q4 MATERIALS SCIENCE, MULTIDISCIPLINARY Korean Journal of Metals and Materials Pub Date : 2023-04-05 DOI:10.3365/kjmm.2023.61.4.301
Hyung Kyu Kim, S. Hong, Jongmin Kim, Min-Chul Kim, Young‐kook Lee
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Abstract

The creep properties of Alloy 690, used as a steam generator tube material in nuclear power plants, were evaluated at 650°C, 750°C, and 850°C. The parameters of creep life prediction models were derived using the Larson-Miller (LM), Manson-Haferd (MH), and Orr-Sherby-Dorn (OSD) models, to use as mechanical properties under a virtual severe accident condition like station black out (SBO). The yield strength (YS) and creep property of Alloy 690 were compared with those of Alloy 600, and the effects of the precipitation behavior of Cr carbides on creep properties were analyzed. The YS of Alloy 600 decreased rapidly above the temperature of 750°C, but the YS of Alloy 690 decreased linearly up to the temperature of 850°C because of the formation of M23C6 carbides. The creep stress exponent (n) of Alloy 690 was between 5 and 6, and this indicated that dislocation creep was the major creep mechanism at the test temperatures. The results of creep tests were well matched with the LM, MH, and OSD models for Alloy 690, and there were no significant differences in accuracy between the models. The stress-rupture test results of Alloy 600 and Alloy 690 using the LM model showed that the decrease in creep strength with rupture time of Alloy 690 was steeper than that of Alloy 600 at high temperatures. This indicated that Alloy 690 was more susceptible to creep degradation under longterm creep conditions. The precipitation of Cr carbides in Alloy 690 increased YS, benefitting creep properties for short-term creep. However, the Cr carbides coarsened significantly under loading conditions at high temperature, and this deteriorated the creep properties for long-term creep.
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Cr碳化物的形成对690合金高温蠕变性能的影响
在650°C、750°C和850°C条件下,对核电站蒸汽发生器管材料Alloy 690的蠕变性能进行了评价。采用Larson-Miller (LM)、Manson-Haferd (MH)和Orr-Sherby-Dorn (OSD)模型推导了蠕变寿命预测模型参数,并将其作为车站停电(SBO)等虚拟严重事故条件下的力学性能。对比了690合金与600合金的屈服强度和蠕变性能,分析了碳化物析出行为对合金蠕变性能的影响。合金600的YS在750℃以上迅速下降,而合金690的YS在850℃以下由于M23C6碳化物的形成而呈线性下降。690合金的蠕变应力指数(n)在5 ~ 6之间,表明在试验温度下,位错蠕变是主要的蠕变机制。蠕变试验结果与Alloy 690的LM、MH和OSD模型吻合较好,模型之间的精度无显著差异。采用LM模型对合金600和合金690进行应力-破裂试验,结果表明:高温下,合金690的蠕变强度随断裂时间的下降幅度大于合金600。这表明690合金在长期蠕变条件下更容易发生蠕变退化。690合金中Cr碳化物的析出提高了YS,有利于短期蠕变的蠕变性能。但在高温加载条件下,碳化物明显变粗,导致长期蠕变性能恶化。
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来源期刊
Korean Journal of Metals and Materials
Korean Journal of Metals and Materials MATERIALS SCIENCE, MULTIDISCIPLINARY-METALLURGY & METALLURGICAL ENGINEERING
CiteScore
1.80
自引率
58.30%
发文量
100
审稿时长
4-8 weeks
期刊介绍: The Korean Journal of Metals and Materials is a representative Korean-language journal of the Korean Institute of Metals and Materials (KIM); it publishes domestic and foreign academic papers related to metals and materials, in abroad range of fields from metals and materials to nano-materials, biomaterials, functional materials, energy materials, and new materials, and its official ISO designation is Korean J. Met. Mater.
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