基于ASME III规范的核级大气排放阀高温部件蠕变疲劳强度研究
Research on Creep Fatigue Strength of High Temperature Components of Nuclear Atmospheric Discharge Valve Based on ASME III Code
摘要: 采用ANSYS软件建立了某核级大气排放阀高温部件(阀体和阀盖)蠕变疲劳分析的力学模型，介绍了基于ASME III规范的蠕变疲劳分析方法。计算考虑两种循环载荷工况：1) 低温工况，模拟正常运行，工作温度为370℃，因阀门打开和关闭而引起压力波动；2) 高温工况，模拟运行瞬态，最高工作温度480℃，有温度波动和压力波动。采用热固耦合方法计算了结构的热应力，与自重、压力及外部载荷产生的机械应力进行组合得到结构的总应力，采用主应力差方法计算结构的交变应力强度，依据ASME III规范进行应力评定。对于低温工况，依据设计疲劳曲线进行疲劳强度校核；对于高温工况，依据ASME III规范的弹性分析方法进行蠕变疲劳损伤评定。分析结果表明，大气排放阀高温部件的疲劳强度和蠕变疲劳性能满足规范要求。
Abstract: A mechanical model for creep fatigue analysis of high-temperature components (valve body and bonnet) of a nuclear atmospheric discharge valve was established by using ANSYS software. The creep fatigue analysis method based on ASME III code was introduced. Two cyclic load conditions were considered in the calculation: 1) Low temperature condition, simulating normal operation, working temperature was 370℃, and pressure fluctuation was caused by valve opening and closing; 2) High temperature condition, simulated the transient operation, the maximum working temperature of 480℃, with temperature fluctuations and pressure fluctuations. The thermal stress of the structure was calculated by thermostructural coupling method, and the total stress of the structure was obtained by combining with the mechanical stress generated by dead weight, pressure and external load. The alternating stress intensity of the structure was calculated by principal stress difference method, and the stress was assessed according to ASME III code. For low temperature conditions, the fatigue strength was checked according to the designed fatigue curve. For high temperature conditions, creep fatigue damage was assessed according to the elastic analysis method of ASME III code. The analysis results show that the fatigue strength and creep fatigue performance of the high temperature components of the atmospheric discharge valve meet the requirements of the specification.
文章引用：尤国英, 刘银芳, 薛蓓蓓, 冯其. 基于ASME III规范的核级大气排放阀高温部件蠕变疲劳强度研究[J]. 核科学与技术, 2025, 13(1): 68-79. https://doi.org/10.12677/nst.2025.131008

参考文献

[1] 郑时波, 张庆国, 张钧浩. “华龙一号”汽轮机旁路系统大气排放阀控制系统的优化[J]. 核科学与工程, 2021, 41(1): 181-188.
[2] American Society of Mechnical Engineers (2015) ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NH: Class 1 Components in Elevated Temperature Service. ASME.
[3] American Society of Mechnical Engineers (2015) ASME Boiler and Pressure Vessel Code, Section III, Division 5: High Temperature Reactors. ASME.
[4] French Society for Design and Construction Rules for Nuclear Island Components (2015) RCC-MRx Code: Design and Construction Rules for Mechanical Components of Nuclear Installations: High Temperature, Research and Fusion Reactors. AFCEN.
[5] EDF Energy (2014) R5 2014 Edition. Assessment Procedure for the High Temperature Response of Structures.
[6] 李笑天, 雒晓卫, 何树延. 高温部件的分析评价方法[J]. 核动力工程, 2011, 32(S1): 40-43.
[7] 龚程, 宫建国, 高付海, 等. 基于应力参量的高温结构蠕变设计准则对比及案例分析[J]. 压力容器, 2019, 36(4): 15-21.
[8] 莫亚飞, 龚程, 高付海, 等. 核电高温设备蠕变强度评价方法对比研究[J]. 压力容器,2022, 39(7): 35-42.
[9] 文静, 房永刚, 路燕, 等. 核安全设备疲劳分析方法与步骤[J]. 原子能科学技术, 2014, 48(1): 121-126.
[10] 刘芳, 轩福贞. 基于ASME标准的高温压力容器高温疲劳强度设计方法比较[J]. 压力容器, 2017, 34(2): 14-20.
[11] 孙英学, 杜娟, 卢岳川. 设计瞬态和疲劳损伤对反应堆压力容器设计寿命的影响分析[J]. 核动力工程, 2009, 30(3): 1-3, 12.
[12] 董冬, 郭效东, 朱成亮, 等. 浮动球球阀疲劳寿命分析[J]. 阀门, 2014(5): 29-33.
[13] 余煜哲, 刘忠伟, 邓英剑. 复杂服役环境下高压阀门疲劳可靠性数值分析[J]. 湖南工业大学学报, 2018, 32(6): 45-50.
[14] 张强升, 陈天敏, 朱博, 等. 核级主蒸汽安全阀热应力分析及疲劳校核[J]. 机械强度, 2019, 41(5): 1266-1270.
[15] 林振浩, 钱锦远, 李文庆, 等. 高温阀门的研究进展[J]. 机电工程, 2020, 37(7): 729-735.
[16] 王海涛, 吴莘馨. 高温气冷堆主蒸汽隔离阀高温蠕变疲劳特性研究[J]. 核动力工程, 2011, 32(S1): 18-21.
[17] 王磊, 谈建平, 于新海, 等. 热力耦合作用下阀门高温结构蠕变疲劳损伤研究[J]. 机电工程, 2023, 40(5): 633-643.
[18] 张洪才, 等. ANSYS Workbench 17.0数值模拟工程实例解析[M]. 第2版. 北京: 机械工业出版社, 2017.