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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Deformation mechanism-based true-stress creep model for SA508 Gr.3 steel over the temperature range of 450-750 degrees C
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Deformation mechanism-based true-stress creep model for SA508 Gr.3 steel over the temperature range of 450-750 degrees C

机译：SA508级钢的变形机理的真应力蠕变模型在450-750摄氏度的温度范围内

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摘要

Stress and temperature effects on the creep behaviors and mechanisms of a typical nuclear reactor pressure vessel material, SA508 Gr.3 steel, are investigated, over the temperature range of 450-750 degrees C and stress range of 10-400 MPa. Because of the importance of creep life prediction for nuclear reactor failure prevention, three creep models are assessed: Orr-Sherby-Dorn (OSD) and Larson-Miller (LM) parameter methods, and deformation-mechanism based true-stress (DMTS) model. The OSD model employs a single activation energy Q and stress exponent n, which shows a large discrepancy between the experimental and predicted time-to-strain (3% and 5%) data with a coefficient of determination (R-2) less than 0.33 over the temperature range of 450-750 degrees C. Both the OSD and LM methods are effective in correlating the time-to-rupture with R-2 similar to 0.84 over a narrow temperature range of 650-750 degrees C. The DMTS creep model, on the other hand, characterizes the creep behavior in three normalized stress regions: low, intermediate and high, as dominated by grain boundary sliding (GBS), intragranular dislocation climb (IDC) and dislocation glide (IDG), respectively. The microstructural characteristics and creep damage mechanisms of SA508 Gr.3 steel are also examined using scanning/transmission electron microscopy to confirm the predominance of the aforementioned creep deformation mechanisms. The DMTS model provides a fully consistent description of the strain-time curves, the minimum creep rates (MCRs) and the time-to-strain/rupture as well. They are all in good agreement with the experimental observations, particularly with R-2 similar to 0.94, 0.995, and 0.79 for time to 3% strain, time to 5% strain, and time to rupture, respectively. These analyses demonstrate that the DMTS model is an effective tool in assessing creep properties of SA508 Gr.3 steel for in-vessel retention. (C) 2019 Elsevier B.V. All rights reserved.
机译：研究了对典型核反应堆压力容器材料的蠕变行为和机理的应力和温度效应，SA508 GR.3钢的温度范围为450-750℃，应力范围为10-400MPa。由于蠕变寿命预测对核反应堆失败预防的重要性，评估了三种蠕变模型：ORR-Sherby-Dorn（OSD）和Larson-Miller（LM）参数方法，以及基于变形机构的真胁迫（DMT）模型。 OSD模型采用单一激活能量Q和应力指数N，其显示实验和预测的时间 - 菌株（3％和5％）数据之间的差异，其测定系数（R-2）小于0.33在450-750℃的温度范围内。OSD和LM方法都有效地将与R-2的时间与0.84相似的狭窄温度范围与650-750℃的窄温度范围有效。DMTS蠕变模型另一方面，在三个归一化应力区域中的蠕变行为表征：低，中间和高，分别由晶界滑动（GBS），intragranulate升降（IDC）和位错滑动（IDG）支配。还使用扫描/透射电子显微镜检查SA508 GR.3钢的微观结构特性和蠕变损伤机制，以确认上述蠕变变形机制的优势。 DMTS模型提供了应变时间曲线，最小蠕变速率（MCR）和时间 - 应变/破裂的完全一致的描述。它们完全是良好的与实验观察结果，特别是与0.94,0.995和0.79相似的R-2，时间为3％菌株，分别为5％的菌株，以及时间破裂。这些分析表明，DMTS模型是评估SA508 GR.3钢的蠕变性能的有效工具，用于血管内部保留。 （c）2019 Elsevier B.v.保留所有权利。

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