主管道安注斜接管嘴疲劳混合分析法研究

在主管道接管嘴疲劳分析中,通常采用简化分析和详细分析2种方法。由于安注斜接管嘴结构比较复杂且经受的压力、温度变化较为剧烈,用简化分析法对其进行疲劳分析时,往往过于保守而导致分析结果不能满足规范要求;采用详细分析法进行分析可以减少保守性,但耗时费力。本文采用简化分析和详细分析相结合的混合分析法对主管道安注斜接管嘴进行疲劳分析,既可以减少计算中的保守性又可以节省计算成本。在混合分析中,通过传热特性试验真实模拟流体与接管嘴之间的传热情况,得到用于计算分析的传热特性参数。分析结果表明,考虑流体传热特性因素的混合分析法能够很好地减少计算保守性,是用于主管道安注斜接管嘴疲劳分析的更加实用有效的方法。     

控制棒驱动机构耐压壳下部密封环应力与疲劳分析

采用有限元分析方法对某核电工程控制棒驱动机构耐压壳下部密封环的2种对接厚度进行了应力和疲劳分析对比,在疲劳分析中采用瞬态分组技术,同时参考RCC-M 2002规范对ANSYS程序中的弹塑性修正因子(Ke)进行解耦修正。结果表明,2种接头厚度的分析结果均满足RCC-M规范中的应力评定准则,其中,较薄密封环结构疲劳分析结果相对更安全,较厚密封环结构在其余工况相对更安全;在疲劳分析中对瞬态进行分组能明显降低使用系数和一次加二次应力之和幅值的保守性;在热和机械共同作用的一次加二次应力之和的幅值较高时,对Ke的修正能明显提高计算结果精度。     

瞬态曲线分段线性化方法研究及其程序实现

核电厂的瞬态数据是相关设备应力分析和评定的必要输入。然而,电厂实际运行记录数据或设计瞬态计算数据通常由时间间隔很短的大量数据点构成,直接作为应力分析的输入将会导致大量不必要的计算。为了简化分析,一般需要将瞬态数据曲线进行分段线性化处理。本文基于最小二乘法,开发了一种瞬态曲线分段线性化的方法,并且通过编写PLTC(PiecewiseLinearization forTransientCurves)程序予以实现。分别采用标准正弦函数曲线和核电厂典型瞬态曲线对本文的方法进行了验证,结果表明,本文的方法和程序能够很好地实现瞬态曲线的分段线性化。本文的研究有助于提高核电厂瞬态曲线分段线性化的效率和精度。     

钛合金材料弹塑性修正因子研究

对核级设备的疲劳分析计算通常是采用美国工程师机械学会(ASME)或法国《压水堆核岛机械设备设计和建造准则》(RCC-M)规定的简化弹塑性疲劳分析方法。进行简化的弹塑性疲劳分析需要确定弹塑性修正因子(Ke)及其相关参数。规范给出了核级设备常用材料的Ke基于大量试验数据拟合的经验公式及其相关系数。但目前,规范并没有提供钛合金材料的这些相关数据。由于试验获取钛合金材料Ke需要耗费大量时间和物力,因此,通过数值分析方法获取钛合金材料的Ke,并验证核级设备常用材料规范提供的经验公式是数值分析方法获取Ke的包络值,同时确定包络的最小保守裕量。以此为依据,确定钛合金材料Ke的表达式及其相关系数,以满足钛合金TA17的简化弹塑性疲劳分析要求。     

钛合金材料弹塑性修正因子研究

对核级设备的疲劳分析计算通常是采用美国工程师机械学会(ASME)或法国《压水堆核岛机械设备设计和建造准则》(RCC-M)规定的简化弹塑性疲劳分析方法。进行简化的弹塑性疲劳分析需要确定弹塑性修正因子(Ke)及其相关参数。规范给出了核级设备常用材料的Ke基于大量试验数据拟合的经验公式及其相关系数。但目前,规范并没有提供钛合金材料的这些相关数据。由于试验获取钛合金材料Ke需要耗费大量时间和物力,因此,通过数值分析方法获取钛合金材料的Ke,并验证核级设备常用材料规范提供的经验公式是数值分析方法获取Ke的包络值,同时确定包络的最小保守裕量。以此为依据,确定钛合金材料Ke的表达式及其相关系数,以满足钛合金TA17的简化弹塑性疲劳分析要求。     

不锈钢管道抗冲击分析应力折减因子研究

为分析不锈钢管道抗冲击弹塑性设计时应力折减因子的保守裕量,采用自重、内压以及冲击载荷,并运用不同的载荷放大因子及线弹性和弹塑性两种计算方法,分别得到了3种载荷独立作用下不锈钢管道的名义弹性应力和实际塑性应变。通过比较分析结果,发现规范中对冲击载荷引起的应力折减因子取为0.25较为保守,提出冲击载荷的应力折减因子取0.2既能满足规范保守性要求又能降低评定标准的过度保守性。     

基于趋势滤波的瞬态曲线协同分段线性化方法研究

核电厂瞬态曲线由数量巨大的数据点构成,无法直接用于疲劳分析计算。因此,合理地对瞬态曲线进行分段线性化处理是进行疲劳分析的前提条件。本文提出一种基于趋势滤波算法的核电厂瞬态协同分段线性化方法,并分别采用折线参考瞬态和真实瞬态曲线对该方法进行了验证。结果表明,本文提出的方法能够准确、合理地对含噪声的瞬态数据进行处理,准确实现瞬态曲线的分段线性化。     

ANSYS用户子程序USERCV在瞬态热分析中的应用

核一级设备的瞬态热分析结果对结构的疲劳、断裂分析评价具有重要影响,而热分析的关键环节是精确确定冷却剂与容器表面之间界面处的热交换系数。本文采用ANSYS用户子程序USERCV实现有限元分析中底层数据的交换,最终实现换热系数的准确施加。本文介绍了USERCV子程序的编写、编译与连接,并结合具体算例给出了应用过程。从结果对比可以看出,USERCV子程序能在一定程度上减少断裂力学评定和疲劳分析的保守性。     

核电厂金属疲劳监测过程中环境影响疲劳评价方法研究

轻水反应堆中金属部件的环境影响疲劳寿命（EAF）问题近年来一直是国内外核安全设备研究和监管所关注的重要问题。本文对日本和美国的相应试验研究数据进行了深入分析,对环境影响疲劳修正系数F_en的计算公式进行了分析讨论,总结出不同金属材料F_en计算结果的保守性以及关键影响因素的敏感性。结合我国的实际情况,借助F_en修正计算公式,给出了一种核电厂金属疲劳监测过程中开展环境影响疲劳的评价方法。结果表明：现阶段可基于核电厂监测的真实瞬态数据采用F_en修正公式对环境影响因子进行估算,对于同类型的金属材料,不同试验环境拟合的F_en公式计算结果非常接近,但EAF问题在金属部件疲劳寿命评估过程中不可忽视。     

核容器法兰密封系统密封性能数值分析

一文提出了一种用于反应堆压力容器法兰密封系统密封分析的瞬态耦合热弹塑性接触有限元分析新方法，编制了完整的瞬态密封分析程序系统。并已成功地用于工程实际问题的分析，和实验结果吻合良好。     

Fatigue — determination of a more realistic usage factor

The ability to use a suitable counting method for determining the stress range spectrum in elastic and simplified elastic-plastic fatigue analyses is of crucial importance for enabling determination of a realistic usage factor. Determination of elastic-plastic strain range using the K_e factor from fictitious elastically calculated loads is also important in the event of elastic behaviour being exceeded. This paper thus examines both points in detail. A fatigue module with additional options, which functions on this basis is presented. The much more realistic determination of usage factor presented here offers various economic benefits depending on the application.     

钛合金TA16弹塑性修正因子数值分析方法研究

本文对核级规范提供的奥氏体不锈钢材料的弹塑性修正因子（KE）的各种敏感因素进行数值验算,确定了不锈钢材料Z2CND18.12(控氮)简化弹塑性疲劳分析所需KE与规范限值之间最小保守裕量为12%。基于钛合金TA16的单轴拉伸、应变循环和应力循环试验,确立了TA16在30 ℃和350 ℃的Chaboche本构模型参数。基于TA16的本构模型参数,对TA16开展各种敏感因素下的弹塑性分析,并参考奥氏体不锈钢的KE表达式和Z2CND18.12(控氮)的KE最小保守裕量迭代计算出TA16的相关系数。TA16的相关系数A、B、C、m、n分别为1.37、1.26、1.37、2.0和0.25。     

A simplified technique for shakedown limit load determination

In this paper, a simplified technique is presented to determine the shakedown limit load of a structure using the finite element method. The simplified technique determines the shakedown limit load without performing lengthy time consuming full elastic-plastic cyclic loading simulations or conventional iterative elastic techniques. Instead, the shakedown limit load is determined by performing two analyses namely: an elastic analysis and an elastic-plastic analysis. By extracting the results of the two analyses, the shakedown limit load is determined through the calculation of the residual stresses developed within the structure. The simplified technique is applied and verified using two bench mark shakedown problems namely: the two-bar structure subjected to constant axial force and cyclic thermal loading, and the Bree cylinder subjected to constant internal pressure and cyclic high temperature variation across its wall. The results of the simplified technique showed very good correlation with the, analytically determined, Bree diagrams of both structures. In order to gain confidence in the simplified technique, the shakedown limit loads output by the simplified technique are used to perform full elastic-plastic cyclic loading simulations to check for shakedown behavior of both structures.     

Fatigue analysis for analytically overloaded piping components and valves in nuclear power plants

Lately, in connection with life extension aspects of power plants, an increasingly accurate determination of the lifetime of components in nuclear stations is being required. In order to assess reliably current fatigue levels in piping systems, variables such as pressure, temperature, and resultant force and moment transients as well as analytical methods which take into account the real operational history must be considered. This paper presents a method for analyzing the transient heat transfer between fluid and pipe wall in order to investigate effects which until now have been assumed conservatively to be caused by a sudden jump in temperature. Further, an example is given showing that the K_e factor approach in current design codes for performing simplified elastic-plastic fatigue analyses is conservative.     

The effect of a single tensile overload on stress corrosion cracking growth of stainless steel in a light water reactor environment

It has been found that a single tensile overload applied during constant load amplitude might cause crack growth rate retardation in various crack propagating experiments which include fatigue test and stress corrosion cracking (SCC) test. To understand the affecting mechanism of a single tensile overload on SCC growth rate of stainless steel or nickel base alloy in light water reactor environment, based on elastic-plastic finite element method (EPFEM), the residual plastic strain in both tips of stationary and growing crack of contoured double cantilever beam (CDCB) specimen was simulated and analyzed in this study. The results of this investigation demonstrate that a residual plastic strain in the region immediately ahead of the crack tips will be produced when a single tensile overload is applied, and the residual plastic strain will decrease the plastic strain rate level in the growing crack tip, which will causes crack growth rate retardation in the tip of SCC.     

基于虚拟激励法的超多点多维激励下管路简化疲劳寿命分析

针对超多点随机振动边界条件下传统随机振动模块计算规模不适用,且传统疲劳寿命分析方法受建模工作量大制约而无法快速完成疲劳寿命分析的问题,本文基于虚拟激励法提出了一种针对管路系统的超多点多维激励的简化疲劳寿命分析方法。通过对比虚拟激励法和传统随机振动模块计算的结构动力学响应,验证虚拟激励法的适用性,并使用管路简化疲劳寿命分析方法和传统疲劳寿命分析方法分析直管结构和三通连接位置的疲劳寿命。结果表明,虚拟激励法计算的随机振动响应精度与传统随机振动模块一致,说明本文方法可突破传统随机振动模块对振动激励点数和频率点的限制;本文方法无需建立详细有限元模型,直管结构的应力及寿命分析结果与精细模型基本一致,三通连接位置的应力及寿命分析结果相比精细模型更加保守。本文研究可为复杂振动管路系统的快速疲劳寿命分析提供理论指导。      

A simplified technique for shakedown limit load determination of a large square plate with a small central hole under cyclic biaxial loading

A simplified technique for determining the shakedown limit load of a structure was previously developed and successfully applied to benchmark shakedown problems involving uniaxial states of stress ( [Abdalla et al., 2007a], [Abdalla et al., 2007b] and [Abdalla et al., 2007c]). In this paper, the simplified technique is further developed to handle cyclic biaxial loading resulting in multi-axial states of stress within the large square plate with a small central hole problem. Two material models are adopted namely: an elastic-linear strain hardening material model obeying Ziegler's linear kinematic hardening (KH) rule and an elastic-perfectly-plastic (EPP) material model. The simplified technique utilizes the finite element (FE) method and employs small displacement formulation to determine the shakedown limit load without performing lengthy time consuming full elastic-plastic cyclic loading FE simulations or conventional iterative elastic techniques. The simplified technique is utilized to generate the shakedown domain for the plate problem subjected to cyclic biaxial tension along its edges. The outcomes of the simplified technique showed very good correlation with the results of analytical solutions as well as full elastic-plastic cyclic loading FE simulations. Material hardening showed no effect on the shakedown domain of the plate in comparison to employing EPP-material.     

Fluid-structure interaction analysis for pressurizer surge line subjected to thermal stratification

Serious mechanical damages such as cracks and plastic deformations due to excessive thermal stress caused by thermal stratification have been experienced in several nuclear power plants. In particular, the thermal stratification in the pressurizer surge line has been addressed as one of the significant safety and technical issues. In this study, a detailed unsteady computational fluid dynamics (CFD) analysis involving conjugate heat transfer analysis is performed to obtain the transient temperature distributions in the wall of the pressurizer surge line subjected to stratified internal flows either during out-surge or in-surge operation. The thermal loads from CFD calculations are transferred to the structural analysis code which is employed for the thermal stress analysis to investigate the response characteristics, and the fatigue analysis is ultimately performed. In addition, the thermal stress and fatigue analysis results obtained by applying the realistic temperature distributions from CFD calculations are compared with those by assuming the simplified temperature distributions to identify some requirements for a realistic and conservative thermal stress analysis from a safety point of view.     

Displacement estimates of pipe elbows prior to plastic collapse loads

The non-differentiability of the plastic dissipation calculated through the Von-Mises yield function leads to convergence difficulties when using mathematical programming to solve Köiter's kinematical formulation of the classical limit analysis. This problem is avoided replacing the plastic dissipation by the strain energy of a fictitious viscoelastoplastic material with a nearly infinite Young modulus. Classical limit analysis can only give information about the limit load multiplier and the plastic collapse mechanism. Based on Zarka's method and using the finite element method and mathematical programming, it is possible to obtain not only the limit load but also an estimate of the elastoplastic displacements. This is very useful because construction codes usually impose limits on the electroplastic displacements. Some pipeline systems are examined using a 1-dimensional shell type finite element to illustrate the procedure. The results obtained are compared with simplified analytical solutions and with alternative numerical results using 2-dimensional shell elements and realistic materials.     

Shakedown analysis of elastic-plastic structures

Behavior of elastic-plastic structures under repetitive and fluctuating loads is considered in this paper. Plastic deformation either stabilizes after a finite number of cycles or continues during the cycling. In the first case the structure is said to have shaken down to the boundary at the loading program. If plastic deformation does not stabilize an elastic-plastic structure becomes unserviceable due to either alternating plasticity when yielding occurs repeatedly in the opposite senses or accumulation of plastic strains and progressive increase of permanent displacements. This paper attempts to survey the shakedown theory, including the accommodation of a structure to the prescribed loading range as well as inadaptation and unserviceability.The notion of shakedown, incremental collapse, ratchetting and alternating plastic deformation are first illustrated with examples. The fundamental theorems on shakedown and inadaptation are presented next, attention being directed to generalizations of the classical Melan and Koiter theorems. Applications of the theorems are given. Available methods for determining the shakedown range on generating self-equilibrated stress fields are discussed. Special techniques applicable to problems involving both dead and fluctuating loads are invoked. Recent studies accounting for inertia forces, geometrical changes, material hardening, variation of material properties with temperature, displacement assessment, etc. are referred to.