摘要
为了研究316不锈钢在蠕变-疲劳交互作用下的影响,开展保载时间的蠕变-疲劳试验和两级加载蠕变-疲劳试验,后者包括先疲劳后蠕变和先蠕变后疲劳两种蠕变-疲劳交互试验。在上述三种试验数据基础上,对316不锈钢的蠕变-疲劳特性进行分析,并对ASME规范的适用性和安全性进行了评价。本研究对蠕变-疲劳试验、ASME规范应用、第四代反应堆高温结构材料的力学特性研究及相关的评定准则具有参考价值。
Background: In super-critical water-cooled reactor, creep-fatigue under high working temperature will affect life of various equipments. Purpose: Understanding characteristics of creep-fatigue interaction correlation is important before evaluating its damage by ASME code. Methods: In order to study creep-fatigue interaction of 316 stainless steel (316SS), three types of creep-fatigue interaction have been taken into consideration in our experiments, which include traditional creep-fatigue interaction subjected to cycling load with hold times at its peak and also creep-fatigue interaction by decoupling creep and fatigue load. Based on the experimental data, the different types of creep-fatigue interaction have been compared and discussed. Moreover, suitability of ASME NH rules in assessing various creep-fatigue interactions of 316SS produced in China is investigated. Results: Creep-fatigue damage envelop of 316SS from ASME can cover the experimental results from the three types of experiments mentioned above. Conclusions: This experimental study is useful as a reference in creep-fatigue interaction experiments, application of ASME code and study of mechanical characteristic of high temperature structural materials in generation IV nuclear power plant.
出处
《核技术》
CAS
CSCD
北大核心
2013年第4期217-221,共5页
Nuclear Techniques