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中国腐蚀与防护学报  2017, Vol. 37 Issue (2): 81-92    DOI: 10.11902/1005.4537.2016.073
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核级不锈钢的热老化研究进展
林晓冬,彭群家(),韩恩厚,柯伟
中国科学院金属研究所 中国科学院核用材料与安全评价重点实验室 沈阳 110016
Review of Thermal Aging of Nuclear Grade Stainless Steels
Xiaodong LIN,Qunjia PENG(),En-Hou HAN,Wei KE
Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
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摘要: 

综述了热老化对核级铸造和焊接奥氏体不锈钢组织、结构和性能的影响、热老化动力学行为以及热老化脆性评估方法与寿命预测等方面的研究进展,分析了不锈钢的热老化脆性机制,指出了不锈钢热老化研究存在的问题及进一步的研究方向。
关键词 ： 核级不锈钢,  热老化,  动力学,  脆性评估,  寿命预测,  脆化机制    
Abstract：

Nuclear grade cast and welded austenitic stainless steels are subjected to thermal aging during long-term service in light water nuclear reactors (LWRs), primarily due to the existence of certain amount of ferrite in the steels. The thermal aging results in degradation of the mechanical and corrosion properties of the steels, which leads to a potential concern to the structural integrity of the relevant LWR components. This paper reviewed the recent research progress of the effect of thermal aging on microstructures and properties of the nuclear grade cast and welded stainless steels, as well as the kinetics, assessment and prediction methods for thermal aging. The mechanism of thermal aging induced embrittlement was discussed. Challenges and trends for the research of thermal aging in the future were also briefly addressed.
Key words： nuclear grade stainless steel    thermal aging    kinetics    embrittlement assessment    lifetime prediction    embrittlement mechanism
收稿日期: 2016-06-07     
基金资助:国家自然科学基金 (51571204)
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林晓冬
彭群家
韩恩厚
柯伟

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林晓冬,彭群家,韩恩厚,柯伟. 核级不锈钢的热老化研究进展[J]. 中国腐蚀与防护学报, 2017, 37(2): 81-92.
Xiaodong LIN, Qunjia PENG, En-Hou HAN, Wei KE. Review of Thermal Aging of Nuclear Grade Stainless Steels. Journal of Chinese Society for Corrosion and protection, 2017, 37(2): 81-92.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2016.073      或      https://www.jcscp.org/CN/Y2017/V37/I2/81

图1  CF8铸造奥氏体不锈钢,308不锈钢焊材和固溶处理的2205双相不锈钢的显微组织[3,27,28]
图2  Fe-Cr二元相图[34,35]和Fe-45%Cr-5%Ni相图的垂直截面[36]
图3  308L不锈钢焊材在335 ℃热老化20000 h后铁素体调幅分解结构[40]
图4  CF8M不锈钢铁素体内Cr含量波动和浓度频率分布[10]
图5  APT Cr面扫图和△Cr随热老化时间的变化情况[41]
图6  不同热老化条件下的CF3M铸造奥氏体不锈钢在铁素体中析出的G相及其选区衍射分析[53]
图7  308L不锈钢焊材在335,365和400 ℃下热老化不同时间后的Charpy-V试样冲击韧性转变曲线[37]
图8  308L不锈钢焊材在焊态和365 ℃下热老化20000 h后的室温冲击断口形貌[37]
图9  不同显微结构转变的动力学曲线示意图[14]
图10  CF8不锈钢的室温冲击韧性随热老化参数P的变化曲线[4]
图11  308L不锈钢焊材中铁素体硬度与SLEPR测试中峰值电流密度的关系[40]及2205不锈钢铁素体硬度与阳极极化测试中二次钝化峰值电流密度的关系[49]
图12  铁素体含量分别为21%,24%和13%的CF8奥氏体不锈钢的lg(CVN)-P关联曲线和下限曲线[87]
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