CRDM管座多道焊焊接残余应力计算方法研究

使用有限元方法,预先分析控制棒驱动机构(CRDM)管座区域过盈配合产生的预应力场,再通过依次模拟多道焊加热和冷却的过程,开展CRDM管座坡口的焊接残余应力数值模拟研究,分析冷装工艺和多道焊焊接残余应力对CRDM管座的共同作用,分析焊道之间的冷却时间的影响,为工程设计和修复提供支持。     

基于模拟件-产品件方法研究反应堆压力容器顶盖与多个CRDM管座焊接残余应力

提出模拟件-产品件有限元数值计算方法研究反应堆压力容器(RPV)顶盖与多个控制棒驱动机构(CRDM)管座焊接的残余应力分布。进行模型件制造和试验测试,获得温度循环、残余应力等数据,针对模拟件残余应力进行数值计算,以试验数据标定模拟件模型和算法并进行优化,最后将优化算法和模型应用于产品件的数值计算。将该方法用于包含2个非中心孔位置J型焊缝的RPV顶盖产品件焊接残余应力算。结果表明:模拟件-产品件的研究方法可应用于核电大型焊接结构的残余应力高效数值分析,CRDM管座焊缝之间的应力叠加效果不明显。     

反应堆控制棒驱动机构管座焊接坡口及密封焊焊缝三维设计

通过分析反应堆控制棒驱动机构管座焊接坡口及密封焊焊缝的平面和空间形状,定义了4条空间的相贯线,提出了管座焊接坡口及密封焊焊缝的三维设计思路与要点;利用UG软件实现了管座焊接坡口及密封焊焊缝的参数化设计,分析了影响管座密封焊焊缝截面积的主要因素.测量结果表明,使用样条法建立的管座焊接截面积误差均控制在0.8%以内.     

控制棒驱动机构上部Ω焊缝堆焊修复结构完整性分析

针对核电厂控制棒驱动机构（CRDM）上部Ω焊缝堆焊修复（WOR）技术,采用数值模拟方法进行了修复结构完整性评估。根据堆焊修复参数制定二维轴对称高斯热源等效输入,并采用ANSYS程序的单元生死技术模拟焊接过程,得到了结构的焊接残余应力。考虑电厂运行的全部瞬态,计算了结构的瞬态应力,并开展了疲劳分析。结合焊接残余应力分析和瞬态应力分析的结果,开展了断裂力学分析。结果表明,WOR结构的疲劳结果、应力强度因子及裂纹扩展等方面均能满足相应的规范要求。      

焊接结构中的残余应力

本文讨论了焊接结构中残余应力的性质,包括其大小、方向性、空间分布、范围和种类。以下因素均会对残余应力产生影响：材料性能、材料制造、焊接构件的几何形状和加工工艺、焊接工艺、焊后处理工艺和服役条件。本文给出了板对接焊缝、管对接环焊缝以及表面堆焊中的残余应力分布实例。这些实例表明,不同几何形状的焊接接头,其残余应力的大小和分布是不同的。本文验证了各构件材料的力学性能、热学性能和相组成对残余应力的影响,以及在焊接过程中残余应力对焊道顺序和焊接中所使用约束的敏感性,并采用管材和压力容器的对接环焊缝的一般范例来进一步阐明测量点到焊缝的距离及焊后热处理对残余应力的影响。残余应力的实测值或模拟计算值存在大的分散性和不确定性。这种分散性可能是由测量点或材料性能的差异等系统因素造成的,或者是由所测数据的实验误差、模拟分析时的错误假定,或者是由预先存在的残余应力、记录不全的焊接或制造工艺和未记录的局部修复等未知因素导致的。为了提高残余应力的预测准确度和降低不确定性,需要更好地记录焊接结构及其零部件材料的制造过程、服役史,并更好地理解和分析许多可能影响残余应力的工艺过程。     

镍基合金压力容器环形焊缝残余应力数值模拟与失效应力分析

根据英国结构完整性评估标准BS7910(2013),考虑焊接残余应力影响,采用失效评估图(Failure Assessment Diagram,FAD)方法对镍基合金压力容器焊接部位内表面裂纹进行安全评估。首先采用有限元分析(Finite Element Analysis,FEA)方法,对压力容器V型、X型坡口环焊缝多层多道对接焊进行数值模拟,获取焊接残余应力分布,并将V型坡口对接焊焊接残余应力曲线与BS7910(2013)标准残余应力分布进行了对比;其次,对BS7910(2013)1级-FAC曲线进行公式化简,在焊接位置考虑残余应力、应力集中、塑性失效因子三因素的影响,对轴向内部半椭圆裂纹进行了失效应力预测。结果表明:残余应力的分布直接影响计算结果,残余拉应力越大,相应失效应力越小;残余应力值和裂纹深度a保持不变,失效应力计算结果随c/a(c为裂纹半长)增大而减小;当c/a比值不变,失效应力值随着a增大而减小。本文焊接残余应力模拟即及失效应力预测方法为以后含缺陷压力容器及管道失效应力计算(寿命预测)提供一定的参考。     

焊接残余应力有限元分析技术研究

本文以岭澳核电站控制棒驱动机构(CRDM)耐压壳Ω焊接为例,应用ANSYS有限元生死单元技术模拟焊接流程,并计算焊接后残余应力的分布,绘制残余应力分布曲线并进行计算结果分析.通过本项目的研究,掌握了焊接残余应力的分析技术,达到了研究目的.     

CRDM中部?密封环堆焊修复裂纹扩展分析

核电厂控制棒驱动机构(CRDM)耐压壳采用?密封环焊接安装在反应堆压力容器顶盖的管座上。一回路水应力腐蚀易诱发?密封环焊缝产生裂纹导致泄漏,需采用堆焊技术进行修复以保证?密封环结构完整性。基于ASME规范中的断裂力学分析方法,针对?密封环堆焊修复的设计结构,开展疲劳和应力腐蚀引起的裂纹扩展分析计算,为?密封环堆焊设计和评定提供参考。     

燃料组件上管座单元件国产化焊接工艺研究

阐述了国产化燃料组件上管座单元件的材料焊接性能及焊接工艺,进行相应的母材熔敷性、均匀性、熔透性以及管座实体焊接试验,摸索出符合技术条件要求的焊接工艺:上管座单元件的焊接接头为无坡口对接形式;采用手工组装点焊+自动焊+微缺陷手工补焊的方法;采用变速焊接,在板簧槽段和收弧段提高焊接速度。采用该工艺开展焊接鉴定,结果均符合技术条件要求。     

铍环电子束焊接温度场和应力场的有限元分析

采用ADINA/ADINAT对铍环电子束焊接过程的温度场和应力场进行了有限元分析 ,结果表明 :铍环焊接过程中焊缝外表面最高温度达 2 73 4℃ ,内表面最高温度仅 3 78℃ ,位于外止口铍钚一侧 ;铍环电子束焊接后 ,在焊缝附近 2 0mm范围内焊接残余应力较大 ,焊缝处于复杂的三维应力状态 ,焊缝根部的残余应力达到最大 ;内外止口铍环由于结构差异 ,焊接残余应力分布并不完全相同。     

Effects of thermal load and cooling condition on weld residual stress in a core shroud with numerical simulation

Stress corrosion cracking (SCC) in the heat affected zone is the primary damage form due to weld residual stress, corrosion and neutron irradiation environment in the core shroud of a boiling water reactor. The distribution of weld residual stress around a weld is necessary to be clarified to evaluate the structural integrity of core shroud for SCC. Moreover, studying the effects of welding parameters on residual stress on reducing the residual stress is very important to suppress the initiation and propagation of SCC.In this paper, we used a finite element method (FEM) to clarify the distribution of weld residual stress around the sixth horizontal weld (H6a) between the lower ring and the cylinder in the core shroud. The simulation results of axial stress were consistent with the experimental results at the inside and outside surfaces of the core shroud, respectively. The effects of thermal loads and cooling conditions were also investigated with the same model. We simulated the welding progress with water cooling on the inside and outside surfaces of the core shroud in order to study the influence of cooling conditions on the residual axial stress around the weld. The simulation results indicated that water cooling decreased the residual axial stress at the same side due to changing the temperature-affected fields. Moreover, with fixing the peak temperatures of weld passes, the simulation results of the distribution of residual axial stress by the thermal loads with different heating time were compared. The simulation results suggested that the heating time was expected to be longer and the heat flux to be smaller for reaching the small tension residual axial stress or even compression stress around the H6a weld.     

反应堆压力容器内部大尺寸环形异种金属焊缝残余应力分布研究

获得反应堆压力容器内部大尺寸环形异种金属焊缝残余应力分布可为反应堆压力容器结构设计和制造工艺优化提供指导,通过设计和制造能够代表产品焊接结构形式的镍基合金和低合金钢异种金属焊接结构模拟件,采用轮廓法测试焊接结构模拟件内部纵向残余应力,采用有限元法模拟计算焊接结构模拟件横向和纵向残余应力,获得了整个异种金属焊接接头残余应力分布特征。结果表明:焊缝区域内部纵向残余应力为拉伸应力,峰值应力达到500 MPa左右,并且表层应力大于内部应力,峰值应力出现在距下表面3 mm和24 mm位置;横向残余应力在焊缝区域从上表面到下表面的分布为拉应力-压应力-拉应力,压缩横向残余应力峰值达到?300 MPa,出现在距下表面约18 mm位置。本文研究可为焊接结构设计提供理论指导。      

Remaining life prediction of the core shroud due to stress corrosion cracking failure in BWRs using numerical simulations

Stress corrosion cracking (SCC) of the welded joints in a reactor core shroud is the primary result of the residual stresses caused by welding, corrosion and neutron irradiation in a boiling water reactor (BWR). Therefore, the evaluation of SCC propagation is important for the safe maintenance of the core shroud. This paper attempts to predict the remaining life of the core shroud due to SCC failures in BWR conditions via SCC propagation time calculations. First, a two-dimensional finite element method model containing H6a girth weld in the core shroud was constructed, and the weld processing was simulated to determine the weld's residual stress distribution. Second, using a basic weld residual stress field, the SCC propagation was simulated using a node release option and the stress redistribution was calculated. Combined with the J-integral method, the stress intensity factors were calculated at depths of 2, 3, 4, 8, 12, 16, 19, 22, 25 and 30 mm in the crack setting inside the core shroud; then, the SCC propagation rates were determined using the relation between the SCC propagation rate and the stress intensity factor. The calculations show that the core shroud could safely remain in service after 9.29 years even when a 1-mm-deep SCC has been detected.     

Predicting welding residual stresses in a dissimilar metal girth welded pipe using 3D finite element model with a simplified heat source

Dissimilar metal welds are commonly used in nuclear power plants to connect low alloy steel components and austenitic stainless steel piping systems. The integrity assessment and life estimation for such welded structures require consideration of residual stresses induced by manufacturing processes. Because the fabrication process of dissimilar metal weld joints is considerably complex, it is very difficult to accurately predict residual stresses. In this study, both numerical simulation technology and experimental method were used to investigate welding residual stress distribution in a dissimilar metal pipe joint with a medium diameter, which were performed by a multi-pass welding process. Firstly, an experimental mock-up was fabricated to measure the residual stress distributions on the inside and the outside surfaces. Then, a time-effective 3-D finite element model was developed to simulate welding residual stresses through using a simplified moving heat source. The simplified heat source method could complete the thermo-mechanical analysis in an acceptable time, and the simulation results generally matched the measured data near the weld zone. Through comparing the simulation results and the experimental measurements, we can infer that besides the multi-pass welding process other key manufacturing processes such as cladding, buttering and heat treatment should also be taken into account to accurately predict residual stresses in the whole range of the dissimilar metal pipe.     

Intergranular stress corrosion cracking behavior of niobium-added Type 308 stainless steel weld overlay metal in a simulated BWR environment

Type 308 stainless steel weld metal as an internal cladding of reactor pressure vessels for boiling water reactors is subject to postweld heat treatment during fabrication and can suffer sensitization depending on carbon and ferrite contents. This sensitization can be avoided by using niobium-added Type 308 weld metal (specified as Type 308 NbL) which was developed for one-layer overlay welding application. In the present study, stress corrosion cracking (SCC) behavior of heat-treated Types 308 and 308NbL weld metals in oxygenated high temperature pure water was evaluated by slow strain rate test and U-bend tests with and without crevice. Every test showed that Type 308NbL weld metals were highly resistant to SCC compared to ordinary Type 308 weld metals. In single U-bend test, one-layer overlay weld metals of Type 308NbL produced by electroslag welding process using wide strip electrodes were crack free over 23,000 h. The U-bend test data of ordinary Type 308 weld metals were successfully analyzed by an SCC reaction model. Using this analysis, the SCC life margin for Type 308NbL over ordinary Type 308 weld metals, expressed as a ratio of respective times to SCC initiation, was estimated to be about 36.     

Design and Analysis of the Laser Robotic Welding System for ITER Correction Coil Case

ITER correction coil (CC) cases have characteristics of small cross section, large dimensions, and complex structure. The cases are made of heavy thick (20 mm), high strength and high toughness 316LN austenitic stainless steel. The laser welding is used for the case closure welding, due to its low heat input and deformation. According to the structural size and feature of the two types of cases, a set of laser welding workstation for the ITER CC case closure welding is designed. A slip plate module for the welding robot is designed to increase its workspace. According to the result of the movement simulation of the welding robots, the workstation is successful to cover all weld seams on the cases. Also, the welding platform and fixtures (includes the special welding tilter of the SCC) of the BTCC case and the SCC cases are designed. To verify the design structural feasibility of the welding tilter of SCC, the structural analysis for the rotating process has been formed in detail by using ANSYS. The simulating results show that the stress of the welding tilter can meet both static and fatigue criteria, and thus the basic structure is valid.     

焊后热处理对16MND5钢焊接组织结构与残余应力的影响

16MND5钢广泛应用于核岛承压容器构件,其焊接接头不可避免地会引入高的残余应力,而焊后热处理可有效消减焊接残余应力以克服应力腐蚀裂纹的影响。本工作利用轮廓法和中子衍射技术研究了焊后热处理对16MND5钢焊接残余应力的影响。结果表明,轮廓法与中子衍射测试结果在趋势和数值上取得了较好的一致性,焊后热处理使焊接态的残余应力峰值从约420 MPa降低至约210 MPa。同时,利用金相法和SEM研究了焊后热处理对焊缝区域组织结构的影响。结果表明,焊后热处理主要表现为贝氏体和少量自回火马氏体的焊缝中心组织转变为回火贝氏体和回火马氏体,热处理后的焊缝区晶粒明显长大。     

Prediction of residual stress distributions due to surface machining and welding and crack growth simulation under residual stress distribution

In nuclear power plants, stress corrosion cracking (SCC) has been observed near the weld zone of the core shroud and primary loop recirculation (PLR) pipes made of low-carbon austenitic stainless steel Type 316L. The joining process of pipes usually includes surface machining and welding. Both processes induce residual stresses, and residual stresses are thus important factors in the occurrence and propagation of SCC. In this study, the finite element method (FEM) was used to estimate residual stress distributions generated by butt welding and surface machining. The thermoelastic-plastic analysis was performed for the welding simulation, and the thermo-mechanical coupled analysis based on the Johnson-Cook material model was performed for the surface machining simulation. In addition, a crack growth analysis based on the stress intensity factor (SIF) calculation was performed using the calculated residual stress distributions that are generated by welding and surface machining. The surface machining analysis showed that tensile residual stress due to surface machining only exists approximately 0.2 mm from the machined surface, and the surface residual stress increases with cutting speed. The crack growth analysis showed that the crack depth is affected by both surface machining and welding, and the crack length is more affected by surface machining than by welding.