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针对核电站蒸汽发生器690合金传热管,通过在室温空气、高温空气以及模拟压水堆高温高压水环境下的疲劳性能测试,研究了环境介质对690合金传热管疲劳寿命的影响,并考察了溶解氧和应变速率等的影响规律,探讨了高温高压水环境下690合金传热管的腐蚀疲劳机理。结果表明,690合金传热管具有足够的疲劳设计安全裕度,且压水堆冷却剂环境对690合金传热管的疲劳寿命影响不明显;溶解氧和应变速率对690合金传热管的腐蚀疲劳寿命的影响也不敏感。推测690合金传热管在高温高压水中的腐蚀疲劳过程主要由膜破裂滑移/溶解机制控制。
Aiming at the heat transfer tube of 690 alloy steam generator of nuclear power plant, the fatigue performance of 690 alloy heat transfer tube under ambient temperature, high temperature air and simulated high temperature and high pressure water environment was studied. The effects of dissolved oxygen and strain rate on the corrosion fatigue mechanism of 690 alloy heat transfer tube under high temperature and high pressure were discussed. The results show that the fatigue life of 690 alloy heat transfer tube has enough fatigue design, and the effect of PWR coolant environment on the fatigue life of 690 alloy heat transfer tube is not obvious. The corrosion rate of 690 alloy heat transfer tube with dissolved oxygen and strain rate The impact of fatigue life is not sensitive. It is speculated that the corrosion fatigue process of 690 alloy heat transfer tube in high temperature and high pressure water is mainly controlled by membrane rupture slip / dissolution mechanism.