摘要
为建立可用于新型锆合金的蠕变模型,本文根据新型锆合金的蠕变试验数据,研究了新型锆合金包壳管在温度为593~673 K、应力在60~160 MPa条件下的堆内外蠕变行为,采用锆合金经典蠕变模型对新型锆合金包壳蠕变性能进行了预测研究,从蠕变行为本构方程出发,研究并建立了新型锆合金包壳蠕变的初步评价方法,并进行了初步验证。验证结果表明:预测值和测量值符合较好,最大相对偏差在25%以内,模型符合锆合金堆内蠕变行为的变化。本研究建立了新型锆合金包壳蠕变模型,表达了其堆内蠕变规律,为新型锆合金的堆内行为的预测提供了支持。
In order to establish a creep model for new zirconium alloy,based on the data from creep test,the creep behavior of the new zirconium alloy cladding tubes at the temperature of 593-673K and the stress of 60-160 MPa was investigated.The classical zirconium alloy creep model was used to predict the creep behavior of the new zirconium alloy clad tube.Based on the constitutive equation of creep behavior,a preliminary evaluation method of creep of new zirconium alloy cladding tube was studied and established,and the preliminary verification was carried out.The verification results show that the predicted values are in good agreement with the measured values,and the maximum relative deviation is whithin 25%.The model is in agreement with the change of creep behavior of zirconium alloy in reactor.In this study,a new zirconium alloy cladding creep model is established,and the model is in agreement with the change of the in-core creep behavior of the zirconium alloy,which provides support for the prediction of the new zirconium alloy's inreactor behavior.
作者
邢硕
蒲曾坪
张坤
焦拥军
戴训
何梁
Xing Shuo;Pu Zengping;Zhang Kun;Jiao Yongjun;Dai Xun;He Liang(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2023年第4期234-239,共6页
Nuclear Power Engineering
基金
国家自然科学基金(U2067221)。
关键词
新型锆合金
蠕变
评价方法
验证
New zirconium alloy
Creep
Evaluaton method
Verification
