国产316LN不锈钢在模拟AP1000一回路水环境中的疲劳行为

一回路水环境下的疲劳性能是核电站主管道设计寿命评估的重要参数。针对国产主管道材料316LN开展了模拟AP1000一回路水环境的低周疲劳试验,分析了疲劳行为和失效机理。研究结果表明:国产316LN峰值应力随应变幅的增大而增大,大应变幅试样在疲劳过程中先后发生了循环硬化、循环软化和失稳,而小应变幅试样在失稳前未发生明显的循环硬化和循环软化;在应变幅由0.2%逐渐增加至1.2%的过程中,疲劳周次从105逐渐降低至102;疲劳断口具有典型的疲劳断口特征,裂纹萌生于试样表面,以穿晶方式垂直于主应力方向扩展,裂纹扩展区具有典型的疲劳辉纹,辉纹上有菱形颗粒状腐蚀产物,环境辅助开裂机制倾向于氢致开裂。     

氢对Ti-4Al-2V钛合金疲劳寿命的影响

采用变截面薄板试样,研究了4种氢含量对Ti-4Al-2V钛合金疲劳寿命的影响。研究结果表明:当拉伸疲劳载荷Dσ大于550MPa时,充氢材料的疲劳寿命高于自然含氢量的材料;在高的Dσ下,含氢量在116~280μg·g-1范围内变化时,对Ti-4Al-2V的寿命影响较小;Dσ降低后,氢含量越高,疲劳寿命越低,同时,Dσ的大小会影响疲劳裂纹的萌生位置。可以认为:材料中固溶氢和氢化物对驻留滑移带(PSB)的影响降低了充氢试样的疲劳裂纹萌生寿命,而高含氢量的Ti-4Al-2V材料在裂纹尖端,通过应力诱导析出氢化物,使裂纹扩展寿命降低。     

侧压对传热管用690合金微动疲劳寿命影响的计算分析与估算公式

微动是蒸汽发生器传热管失效的一个主要原因,揭示传热管用690合金的微动疲劳十分重要。本文通过有限元模型和自编程序计算分析了690合金与抗震条间平-平面接触副微动疲劳裂纹萌生寿命,重点研究了侧压对微动疲劳寿命的影响。结果表明,侧压下的裂纹萌生寿命远低于其标准疲劳寿命,降低程度与微动接触状态和微动磨损均有关。在此基础上提出了一个考虑侧压影响的微动疲劳寿命估算公式。该经验公式具有较简单的解析表达式,且对疲劳寿命的计算较为保守,可方便地用于工程设计和寿命预估     

应变幅对国产锻造奥氏体不锈钢环境疲劳寿命影响的试验研究

为验证模拟压水堆核电站冷却剂服役环境对国产锻造主管道用奥氏体不锈钢疲劳寿命的影响,采用高温高压循环水疲劳测试系统对从产品锻件取样加工后的标准试样进行了低周疲劳试验,分析了试验数据与美国机械工程师学会(American Society of Mechanical Engineers,ASME)规范平均/设计疲劳曲线的关系,获得了应变幅对奥氏体不锈钢环境疲劳寿命的影响规律,并初步评价了ASME规范设计疲劳曲线和环境疲劳修正系数的适合性。     

压水堆核电厂主管道窄间隙自动焊焊丝研究

根据窄间隙自动焊工艺及主管道母材特点,在ER316L焊材基础上研究与主管道自动焊技术相匹配的专用焊材。通过模拟焊接试验和热裂纹试验验证了自动焊焊材的稳定性、可焊性,并对其焊缝疲劳寿命进行试验。研究结果证明新开发的自动焊焊材与主管道窄间隙自动焊工艺相匹配,焊缝接头综合性能良好。     

不同材料的核电厂主管道LBB评估对比研究

我国核电厂主管道的材料主要有铸造奥氏体不锈钢(CASS)和锻造不锈钢(WSS)。针对CASS和WSS两种材料的主管道,依据美国核管会的SRP3.6.3进行主管道硬前漏(LBB)评估的对比研究。考虑热老化效应获取可信的材料性能数据,根据材料性能差异采用极限载荷法或J积分撕裂模量汇交法计算临界裂纹尺寸。根据Henry均匀非平衡双相流模型计算泄漏裂纹尺寸,并通过环向表面裂纹和贯穿裂纹的扩展分析论证了裂纹疲劳扩展不会导致管道的突然断裂。研究结果表明,WSS材料和CASS材料相比具有更好的LBB性能。     

1Cr18Ni9Ti管道焊缝金属疲劳短裂纹萌生与早期扩展

复型研究了1Cr8N9Ti管道焊缝金属的疲劳短裂纹萌生与早期扩展特点，结果表明，有效短裂纹萌生于与管道内外表面一致的试样表面局部区域中delta铁素体与基质的界面，早期扩展具有显著微观结构效应特征，最大障碍尺度约为40μm，与焊缝金属特征微观组织结构――柱状晶中富delta铁素体带距离一致，该尺度范围。由于强微观结构约束，短裂纹密度较高并逐渐增加；尺度不规则扩展，直到若干较长短裂纹发生合并形成导致试样失效的主导短裂纹。这一过程通常称为“微观结构短裂纹（MSC）“阶段，主导短裂纹及其发路径上的短裂纹对疲劳损伤做出直接贡献，可分别称为“主导有效短裂纹（DESFC）“和“有效短裂纹（ESFCs）“，为描述该阶段不规则行为，有必要引入尺度等于ESFCs尺度均值的虚裂纹即MSC阶段DESFC的概念，该阶段DESFC尺度恒定增加，扩展率恒减小。     

锆-4的反复弯曲高周疲劳性能及其显微组织

测定了再结晶状态锆－４合金反复弯曲高周疲劳寿命曲线,得出其疲劳极限约为２５０ＭＰａ。疲劳试样用ＳＥＭ观察表明：锆－４表面为波纹状滑移特征。驻留滑移带、晶界是锆－４主要的疲劳裂纹萌生区域。疲劳变形亚结构的ＴＥＭ分析表明：｛１０１０｝柱面滑移与孪生是其主要的变形方式;锆－４典型的位错组态是两组或多组平行位错线。与纯锆相比,锆－４更易产生交滑移。     

敏化处理对316NG奥氏体不锈钢疲劳裂纹扩展行为的影响

在模拟压水堆腐蚀环境条件下,进行了未敏化与725℃敏化处理的316NG奥氏体不锈钢腐蚀疲劳实验。采用扫描电镜(SEM)、能谱分析仪(EDS)、金相显微镜(OM)分析了试样微观结构、偏析相化学成分及裂纹扩展状况,研究了材料疲劳裂纹扩展行为。研究结果表明:敏化处理可显著抑制316NG奥氏体不锈钢在腐蚀环境中的疲劳裂纹扩展;裂纹扩展速率由未经敏化处理的2.21×10~(-4) mm/次减小到敏化处理10min的1.02×10~(-4) mm/次。敏化处理试样的偏析相颗粒数量增多,萌生的支裂纹也增多,导致裂纹扩展速率减小。但是,敏化处理会导致偏析相颗粒中Cr元素含量增加,颗粒附近的基体成为贫铬区,电化学腐蚀加剧,促进裂纹的扩展。     

氢及氢化物对锆合金疲劳裂纹扩展速率的影响及估算

采用紧凑拉伸（CT）试样．研究了不同氢含量的Zr-4及Zr-Sn-Nb合金在室温下疲劳加载裂纹扩展（dα/dN）行为．用扫描电镜观察了断口形貌。结果表明，氢含量对疲劳裂纹扩展速率影响微弱，疲劳断裂受通常的裂纹萌生、稳态扩展和瞬间断裂机制控制。根据疲劳裂纹扩展机理．导出了裂纹扩展门槛值△Kth的关系式．得出了一个描述疲劳裂纹扩展速率油（dα/dN）与材料性能常数之间的关系式，该关系式可用于预测材料的疲劳裂纹扩展速率。用锆合金实验数据对（dα/dN）预测表达式进行验证．结果表明，预测值与实验值吻合较好。     

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。      

阀门密封结构的渗漏特性数值分析

以核反应堆系统中的安全阀密封结构为研究对象,建立了基于多孔介质理论的密封结构粗糙表面三维模型,采用Darcy定律推导了密封结构泄漏率的计算公式,研究了粗糙度、自相关长度、密封比压对表面特征的影响,以及粗糙度、密封面接触宽度对泄漏率的影响。结果表明,粗糙度与密封性能并非是线性关系,仅以粗糙度作为密封性能的评价指标是有局限性的;在粗糙度一定的情况下,自相关长度也会对密封界面孔隙率、渗透率产生影响,从而影响安全阀的密封性能;密封比压减小导致接触高度增大,使得阀座阀瓣间的孔隙率迅速增大,造成密封结构的渗漏特性增强;粗糙度的增大使得泄漏率呈非线性增大趋势,密封面接触宽度的增加使泄漏率线性减小。      

Thermal stress analysis for fatigue damage evaluation at a mixing tee

Fatigue cracks have been found at mixing tees where fluids of different temperature flow in. In this study, the thermal stress at a mixing tee was calculated by the finite element method using temperature transients obtained by a fluid dynamics simulation. The simulation target was an experiment for a mixing tee, in which cold water flowed into the main pipe from a branch pipe. The cold water flowed along the main pipe wall and caused a cold spot, at which the membrane stress was relatively large. Based on the evaluated thermal stress, the magnitude of the fatigue damage was assessed according to the linear damage accumulation rule and the rain-flow procedure. Precise distributions of the thermal stress and fatigue damage could be identified. Relatively large axial stress occurred downstream from the branch pipe due to the cold spot. The variation ranges of thermal stress and fatigue damage became large near the position 20° from the symmetry line in the circumferential direction. The position of the cold spot changed slowly in the circumferential direction, and this was the main cause of the fatigue damage. The fatigue damage was investigated for various differences in the temperature between the main and branch pipes. Since the magnitude of accumulated damage increased abruptly when the temperature difference exceeded the value corresponding to the fatigue limit, it was suggested that the stress amplitude should be suppressed less than the fatigue limit. In the thermal stress analysis for fatigue damage assessment, it was found that the detailed three-dimensional structural analysis was not required. Namely, for the current case, a one-dimensional simplified analysis could be used for evaluating the fatigue damage without adopting the stress enhancement factor K_t quoted in the JSME guideline. The results also suggested that, for a precise assessment of the fatigue damage at a mixing tee, the effect of multi-axial stress on the fatigue life together with the mean stress effect should be taken into account.     

Zr-Sn-Nb薄片合金高温低周疲劳行为

采用Zr-Sn-Nb合金薄片漏斗试样,完成了室温和500℃高温下的低周疲劳试验,提出基于漏斗根部节点轴向应变的疲劳损伤等效假设。根据有限元分析,建立了Zr-Sn-Nb合金室温和高温下薄片漏斗试样测试应变到漏斗根部轴向应变的转换模型。结合低周疲劳试验结果,建立了在室温和500℃高温条件下用于估算Zr-Sn-Nb合金疲劳寿命的Manson-Conffin模型。结果表明:Zr-Sn-Nb合金具有循环稳定性;高温严重影响了Zr-Sn-Nb合金低应变幅下的疲劳寿命,随着应变幅的增加,温度影响趋弱。     

Low cycle fatigue of welded joints: new experimental approach

To take into account the reduced fatigue strength of welded joints, a reduction life factor applied on fatigue curves (J_f value) was introduced into the RCC-MR [Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, AFCEN, 1993], for the design and construction of fast breeder reactors. To better assess this factor, previous work showed that mechanical behavior of a welded assembly is influenced by the geometry of the weld and by the interaction of the different cyclic plastic behavior of the two materials: base metal (BM) and weld metal (WM). A new procedure (named FFAST) was performed on welded joint specimens extracted from butt-welded pipe connections (uniaxial tensile–compressive load). An innovative experimental approach is proposed to study the local mechanical behavior of the welded joint specimens and then determine the J_f parameter. The main advantage of the method is to avoid problems due to the relative stiffness of weld part versus the BM part of the specimen. A continuous recording of the stress and strain in the weld allows an estimation of the mechanical behavior and finally the fatigue life of the joint. Observations of the crack surface show two different crack initiation zones near the weld depending on the load level. Calculations of the tests and comparison with experimental results are presented. These studies make it possible to assess in a practical way the J_f design method. It appears that J_f value cannot be considered as a single value for it is influenced by several factors depending on the weldment and on the load level.     

核级不锈钢管座焊接区与母材区疲劳裂纹扩展性能对比研究

焊接接头广泛应用于核电站管座处,而疲劳裂纹扩展是导致焊接接头失效的重要原因之一。因此,研究焊接区材料的疲劳裂纹扩展和寿命预测方法对准确预测焊接接头的寿命具有重要意义。本文以核电厂常用的304L不锈钢焊缝材料为对象,研究不同载荷比、不同取样方向对疲劳裂纹扩展速率的影响;基于试验数据建立焊缝材料的疲劳裂纹扩展速率模型,并与美国机械工程师协会（ASME）标准中奥氏体钢进行对比。结果表明:不同取样方向对焊缝疲劳裂纹扩展速率的影响不大,但载荷比对其有较大影响,较低载荷比下,焊缝的疲劳裂纹扩展速率在某个应力强度因子幅值（?K）前高于母材的疲劳裂纹扩展速率,在其之后则低于母材,而较高载荷比下则恰恰相反。      

Thermal fatigue damage evaluation of a PWR NPP steam generator injection nozzle model subjected to thermal stratification phenomenon

Thermal stratification phenomenon with the same thermodynamic steam generator (SG) injection nozzle parameters was simulated. After 41 experiments, the experimental section was dismantled; cut and specimens were made of its material. Other specimens were made of the preserved pipe material. By comparing their fatigue tests results, the pipe material damage was evaluated. The water temperature layers and also the outside pipe wall temperatures were measured at the same level. Strains outside the pipe in 7 positions were measured. The experimental section develops thermal stratified flows, stresses and strains caused enlargement of material grain size and reduction in fatigue life.     

Thermal frequency response studies of a hollow cylinder subject to loads of different amplitude and shape

Thermal fatigue is an important degradation mechanism, which must be considered in life management of nuclear plant piping systems. The analysis is very complex due to a number of complicating factors, with the determination of the load as the primary one. There is clearly a need for simplified engineering approaches, such as simulating the spectrum load by a constant frequency thermal load with the nominal temperature difference between mixing fluids. The fatigue life is determined by the frequency that gives the shortest life using fatigue curves for initiation and Paris law for crack propagation. This paper analyses three aspects that affect the conservatism of such an approach: the thermal load shape (sinusoidal or square shaped), the structural boundary conditions at the edges of the modelled pipe (traction free or clamped) and the defect shape (circumferential or elliptic). Furthermore it is shown how the methodology can be used to determine screening criteria, i.e. a lower limit of the temperature difference below which there will be no component failure due to thermal fatigue.