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	核电站铸造奥氏体不锈钢热老化试验设计
	余伟炜 ; 姜家旺 ; 尤磊 ; 薛飞 ; 刘伟 ; 束国刚 ; YU Weiwei ; JIANG Jiawang ; YOU Lei ; XUE Fei ; LIU Wei ; SHU Guogang
	2016-03-30 ; 2016-03-30
关键词	铸造奥氏体不锈钢 热老化 老化温度 激活能 cast austenitic stainless steel thermal aging ageing temperature activation energy TG260
其他题名	Test Design for Thermal Aging of Cast Stainless Steel in Nuclear Power Station
中文摘要	为验证一回路关键部件铸造奥氏体不锈钢(CASS)在整个寿期内的适用性,结合CASS部件运行期间的主要老化机理,对核电站铸造奥氏体不锈钢的热老化试验设计进行研究。通过对CASS材料的老化机理分析,结合加速老化试验的基本原理Arrhenius公式,分析了激活能Q、老化温度TS和老化时间t对热老化试验的影响,并得出如下结论:对于核电用CASS部件,热老化的加速老化试验温度建议值最高不超过400℃,试验过程中需严格控制加热温度的均匀性和稳定性,同时需要结合激活能值设计可覆盖设备整个寿期的试验,为准确把握材料的老化特征,需合理设置取样的时间间隔。; To verification the applicability of cast austenitic stainless steel(CASS) components during the whole lifetime in nuclear power plant, a investigation on the thermal aging test design parameters were carried out. According to the analysis on the aging mechanism of CASS material, combined with the Arrhenius equation which is the basic principles of accelerated aging tests, the effect of the activation energy Q, aging temperature TS and aging time t for thermal aging test were analysised. According to the results, it suggests that the accelerated aging temperature should not exceed the maximum recommended temperature 400 ℃ for CASS, and the uniformity and stability of heating temperature should be strictly controlled during the test. Simultaneously requires a combination of activation energy values designed to cover the entire life of the components, and a reasonable sampling interval should be set to grasp the characteristics of aging.
语种	中文 ; 中文
内容类型	期刊论文
源URL	[http://ir.lib.tsinghua.edu.cn/ir/item.do?handle=123456789/141641]
专题	清华大学
推荐引用方式 GB/T 7714	余伟炜,姜家旺,尤磊,等. 核电站铸造奥氏体不锈钢热老化试验设计[J],2016, 2016.
APA	余伟炜.,姜家旺.,尤磊.,薛飞.,刘伟.,...&SHU Guogang.(2016).核电站铸造奥氏体不锈钢热老化试验设计..
MLA	余伟炜,et al."核电站铸造奥氏体不锈钢热老化试验设计".(2016).

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