首页> 外文会议>International Symposium on Safety and Structural Integrity; 20051208-10; Jeju(KR) >Socket Weld Integrity in Nuclear Piping Under Fatigue Loading Condition
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Socket Weld Integrity in Nuclear Piping Under Fatigue Loading Condition

机译:疲劳载荷条件下核管道的承插焊完整性

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The purpose of this paper is to evaluate the integrity of socket weld in nuclear piping under the fatigue loading. The integrity of socket weld is regarded as a safety concern in nuclear power plants because many failures have been world-widely reported in the socket weld. Recently, socket weld failures in the chemical and volume control system (CVCS) and the primary sampling system (PSS) were reported in Korean nuclear power plants. The root causes of socket weld failures were known as the fatigue due to the pressure and/or temperature loading transients and the vibration during the plant operation. The ASME Boiler and Pressure Vessel (B & PV) Code Sec. III requires 1/16 inch gap between the pipe and fitting in the socket weld with the weld leg size of 1.09t_1, where t_1 is the pipe wall thickness. Many failure cases, however, showed that the gap requirement was not satisfied. In this paper, the socket weld integrity under the fatigue loading was evaluated using three-dimensional finite element analysis considering the requirements in the ASME Code. Three types of loading conditions such as the deflection due to vibration, the pressure transient ranging from P=0 to 15.51 MPa, and the thermal transient ranging from T=25 ℃ to 288 ℃ were considered. The results are as follows; (1) The socket weld is susceptible to the vibration where the vibration levels exceed the requirement in the ASME Operation and Maintenance (OM) Code [9]. (2) The effect of pressure or temperature transient load on socket weld in CVCS and PSS is not significant owing to the low frequency of transient during plant operation. (3) 'No gap' is very risky to the socket weld integrity for the systems having the vibration condition to exceed the requirement specified in the ASME OM Code and/or the transient loading condition from P=0 and T=25 ℃ to P=15.51 MPa and T=288 ℃.
机译:本文的目的是评估疲劳载荷下核管道承插焊的完整性。承插焊的完整性在核电站中被视为安全问题,因为在承插焊中已报道了许多故障。最近,韩国核电厂报告了化学和体积控制系统(CVCS)和一次取样系统(PSS)的承插焊故障。承插焊故障的根本原因是由于工厂运行期间的压力和/或温度负荷瞬变以及振动引起的疲劳。 ASME锅炉和压力容器(B&PV)法规第二节。 III要求管与承插焊中的管件之间有1/16英寸的间隙,焊脚尺寸为1.09t_1,其中t_1是管壁厚度。但是,许多失败案例表明差距要求没有得到满足。在本文中,考虑了ASME规范的要求,使用三维有限元分析对疲劳载荷下的承插焊缝完整性进行了评估。考虑了三种类型的载荷条件,例如振动引起的挠度,压力瞬变范围从P = 0到15.51 MPa,热瞬变范围从T = 25℃到288℃。结果如下: (1)如果振动水平超出ASME操作和维护(OM)法规[9]的要求,则承插焊容易受到振动的影响。 (2)由于工厂运行期间瞬态频率较低,因此压力或温度瞬态载荷对CVCS和PSS中承插焊的影响不明显。 (3)对于振动条件超过ASME OM规范和/或从P = 0和T = 25℃到P的瞬态载荷条件的系统,“无间隙”对承插焊完整性有很大的风险= 15.51MPa,T = 288℃。

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