核电用316H不锈钢的蠕变性能评估  

Creep Data Prediction for Type 316H Stainless Steel Served in Nuclear Power Plant

作　　者：李昂[1] 吴福[1] 高蔚[1] 张毅[1] Li Ang;Wu Fu;Gao Wei;Zhang Yi(Innovation Center of Nuclear Materials for National Defense Industry,Science and Technology on Particle Transport and Separation Laboratory,Institute of Physical and Chemical Engineering of Nuclear Industry,Tianjin 300180,China)

机构地区：[1]核工业理化工程研究院国防科技工业核材料技术创新中心粒子输运与富集技术重点实验室,天津300180

出　　处：《稀有金属材料与工程》2021年第2期531-536,共6页Rare Metal Materials and Engineering

基　　金：中核集团青年英才计划菁英项目(CNNC2019YTEP-IPCE01)。

摘　　要：通过对核电用316H不锈钢的蠕变数据分析,利用速率温度参数模型拟合得出材料蠕变本构方程。根据相关统计检验方法,确定了材料的蠕变可靠度函数。结合Z’参数的数据分布,分别得出316H不锈钢蠕变应力-RTP参数-可靠度曲线和温度-容许应力-可靠度曲线。结合ASME的评价规范,确定了316H不锈钢在550~700℃下的容许应力。结果表明,基于RMB’模型的蠕变本构方程在拟合精度方面优于其他传统模型。实测数据均位于蠕变可靠性模型预测结果的99.7%置信区间内。该模型可以较好地评估316H不锈钢的稳态蠕变性能及容许应力。Creep life prediction is an important issue for components used for nuclear breeders at high temperature. Through analysis on creep data of 316 H stainless steel served in reactor vessels, the steady state creep rate equation was obtained by rate temperature parameter model. Reasonable statistical test results supported the reliability function of creep property. σ-RTP-R curves and T-[σ]-R curves were proposed for 316 H stainless steel based on the distribution of Z′-parameter in this research. The allowable stresses in service temperatures from 550 °C to 700 °C are also obtained according to the standard methods specified in ASME BPVC. The results demonstrate that RMB’ model has not only good precision in comparison of other existent creep models, but also high prediction accuracy. The experimental creep data completely drop into the 99.7% confidence interval of predicted results by reliability function. The steady state creep behavior and allowable stress of 316 H stainless steel in experimental conditions can be well evaluated by the present model.

关 键 词：316H不锈钢 蠕变性能 速率温度参数模型 Z’参数 容许应力 

分 类 号：TG142.71[一般工业技术—材料科学与工程] TG111.8[金属学及工艺—金属材料]