摘要
对压水堆核电厂一回路设备用国产SA-508 Gr.3 Cl.1低合金钢(简称SA-508-Ⅲ-1钢)进行室温和320℃空气环境,以及模拟压水堆一回路水环境下的疲劳性能试验研究,获得国产SA-508-Ⅲ-1钢在空气环境下的疲劳寿命最佳拟合曲线(平均曲线)。在此基础上,对影响国产SA-508-Ⅲ-1钢在压水堆核电厂一回路水环境下疲劳性能的应变速率、温度和溶解氧含量等参数的影响规律进行研究,获得各影响参数的影响函数方程。基于获得的各影响参数的函数方程,建立国产SA-508-Ⅲ-1钢的环境影响疲劳修正因子F_(en)预测模型。本文获得的压水堆核电厂一回路水环境下国产SA-508-Ⅲ-1钢的疲劳寿命都位于95%置信度限值(10^(±2σ))范围内,验证了本文预测模型的有效性。同时,本文获得的压水堆核电厂一回路水环境下国产SA-508-Ⅲ-1钢的疲劳寿命与美国阿贡国家实验室(ANL)模型所预测的寿命相比,也都位于95%置信度限值(10^(±2σ))范围内,说明ANL模型可用于国产SA-508-Ⅲ-1钢的疲劳寿命预测。本文获得的国产SA-508-Ⅲ-1钢的环境影响疲劳预测模型与ANL模型相比,更适用于国产SA-508-Ⅲ-1钢的寿命预测,为国内第3代核电厂一回路设备考虑压水堆一回路水环境影响的疲劳设计提供参考。
The US Nuclear Regulatory Commission issued regulatory guideline RG 1.207 in 2007 and upgraded it in 2018,which not only requires the design of new nuclear power plants to consider the impact of coolant environment on the fatigue life of nuclear level 1 components,but also requires inservice nuclear power plants to consider environment assistant fatigue(EAF)issues when updating their operating licenses.Over the past 30 years,the Argonne National Laboratory(ANL)in the United States and countries such as Japan have obtained fatigue test results in high temperature and high pressure water environments for primary circuits through extensive simulations.EAF models for primary equipment and pipeline materials in nuclear power plants have been established,and technical support documents NUREG/CR-6909 for RG 1.207 guidelines have been released.Due to the fact that the ANL model is based on experimental data from countries such as the United States and Japan,the EAF test data for domestic SA-508-Ⅲ-1 steel is limited,and the test data has not yet been included in the ANL model.Therefore,it is necessary to simulate the fatigue performance of domestic nuclear materials in a primary water environment,verify the applicability of the ANL model to domestic low-alloy steel materials,and develop an environmental fatigue model for domestic materials,provide a design basis for fatigue design,safety review,and life assessment of primary equipment in third-generation nuclear power plants in China.The fatigue properties of domestic SA-508-Ⅲ-1 steel used in primary loop equipments of PWR nuclear power plant at room temperature,320℃air environment and simulated PWR primary loop water environment were studied,the best fitting curve(average curve)of fatigue properties of domestic SA-508-Ⅲ-1 steel was obtained.Based on this,the effects of strain rate■,temperature(T)and dissolved oxygen(DO)on the fatigue properties of domestic SA-508-Ⅲ-1 steel in the primary water environment of PWR nuclear power plant were studied,based on the functional equations of the influencing parameters,the F_(en)prediction model of the EAF correction factor of domestic SA-508-Ⅲ-1 steel was established.At the same time,comparing to the predicted life of ANL model,the fatigue life of domestic SA-508-Ⅲ-1 steel in the water environment of PWR primary loop is within the limit of 95%confidence limit(10^(±2σ)),which shows that the ANL model can be used to predict the fatigue life of domestic SA-508-Ⅲ-1 steel.Comparing with ANL model,the fatigue prediction model of environmental assistant fatigue obtained by this paper is more suitable for fatigue life prediction of domestic SA-508-Ⅲ-1 steel,which can be used as a reference for the design of the primary loop equipment considering environmental assistant fatigue effect for the third generation nuclear power plant.
作者
沈睿
刘畅
唐力晨
王秉熙
SHEN Rui;LIU Chang;TANG Lichen;WANG Bingxi(Shanghai Nuclear Engineering Research&Design Institute Co.,Ltd.,Shanghai 200233,China)
出处
《原子能科学技术》
北大核心
2025年第1期151-159,共9页
Atomic Energy Science and Technology
作者简介
通信作者:沈睿。
