基于统一曲线法的反应堆压力容器防脆断承压热冲击分析Pressurized Thermal Shock Analysis of the Reactor Pressure Vessel for Resistance to Brittle Fracture Based on Unified Curve Method
杜爱国,杨兴旺,施春丰,马连骥
摘要(Abstract):
田湾核电厂将3、4号机组硼水贮存系统水箱运行温度从70℃调整至20℃,以降低水箱钢衬里应力腐蚀的风险。水箱运行温度的调整会影响反应堆压力容器(RPV)的防脆断设计分析结论,需重新进行评价。采用统一曲线法对RPV2号焊缝进行了承压热冲击分析,并与采用初始设计方法的分析结果进行对比。结果表明,在水箱运行温度为20℃条件下RPV满足防脆断设计要求,采用统一曲线法评价时RPV具有更大的设计寿命容量。
关键词(KeyWords): 反应堆压力容器;承压热冲击;统一曲线法;防脆断
基金项目(Foundation):
作者(Author): 杜爱国,杨兴旺,施春丰,马连骥
参考文献(References):
- [1]初起宝,刘维平,马静娴,等.田湾核电站反应堆压力容器承压热冲击分析[J].原子能科学技术,2015,49(9):1619-1623.
- [2]核动力装置设备和管道强度计算规范[S].ПНАЭГ-7-002-86,莫斯科,1989.
- [3]Margolin B Z. A new engineering method for prediction of the fracture toughness temperature dependence fo RPV steels[J]. Int. J.Pres. Ves. Piping,2003,80:817-829.
- [4]Margolin B Z. Futher improvement of the Prometey model and Unified Curve method.Part 2. Improvement of the Unified Curve Method[J]. Eng. Fract.Mech.,2018,191:383-402.
- [5]Margolin B Z. On issue of comparison of the Unifeid Curve and Master Curve methods and application for RPV structural integrity assessment[J]. Strength of Materials,2016,48(2):227-250.
- [6]Calculation on resistance to fragile destruction of body of water-water power reactors at a design stage[S]. RDEO1.1.2.99.0920—2014,“Rosenergoatom Concern”,2014.
- [7]Analytical report of brittle fracture resistance of the reactor vessel of TNPP Units 3&4[R]. 428M-Пр-438.Mossow:ОKB,2015.
- [8]Calculation of reactor pressure vessel on resistance to fragile destruction in accordance with a technique“Calculation on resistance to fragile destruction of body of water-water power reactors at a design stage”[R]. 428M-Пр-717. Mossow:ОKB,2019.