溶解氧含量对国产化锻造主管道316LN不锈钢环境促进疲劳寿命的影响

在模拟核电厂一回路高温高压水环境中，对国产化锻造主管道用316LN不锈钢开展了疲劳试验，分析了应变速率和溶解氧(DO)含量对不锈钢环境促进疲劳(EAF)寿命的影响。结果表明：在不同DO含量下，试样EAF断口均呈典型的多裂纹源疲劳开裂特征，疲劳辉纹明显；断口上覆盖的腐蚀产物主要为富Fe、Cr、Ni的尖晶石氧化物，随着DO含量的增加，氧化物颗粒数量增加、尺寸变大；在不同DO含量下EAF寿命偏差不超过30%,无明显统计差别；结合不同的统计模型可知，在低应变速率(0.1×10^-4～0.1×10^-3 s^-1)下DO含量对316LN不锈钢EAF寿命的影响才会比较明显；在建立较为精确的统计模型时，需要细分应变速率范围，并考虑DO含量的影响。     

316Ti不锈钢在模拟核电高温高压水中的腐蚀疲劳裂纹断口研究

研究了轻水堆核电站关键设备材料316Ti不锈钢在模拟核电高温高压水环境下的低周疲劳裂纹断口,讨论了疲劳裂纹扩展、断口特征及环境致裂机理。结果表明,疲劳裂纹为穿晶扩展,且呈折线状,裂纹之间相互交叉、连接、分叉呈现出典型的多裂纹特征;高变速率时裂纹短且数目多,低应变速率时裂纹长但数目少,并且高应变速率的辉纹间距小于低应变速率时的;裂纹尖端产生严重塑性变形,并伴有一些滑移带生成,裂纹尖端或者两侧铁素体/基体界面出现二次裂纹。讨论了裂纹扩展滑移溶解机理,实验结果证实了力学和电化学反应协同作用促进了疲劳裂纹扩展,其扩展机理可用滑移溶解模型解释。     

核级316LN不锈钢弯管在高温高压水中的应力腐蚀裂纹扩展行为

采用直流电位降(DCPD)技术,实现了在模拟核电一回路高温高压水环境中对核级316LN不锈钢(SS)弯管材料应力腐蚀裂纹扩展的实时监测,同时利用扫描电子显微镜(SEM)和电子背散射衍射(EBSD)技术对试样断口及裂纹扩展路径进行观察。结果表明,在270~330℃范围,316LN SS弯管材料在高温高压水环境中的应力腐蚀裂纹扩展速率随着温度的升高而单调增加,其裂纹扩展的表观激活能(E_(aae))为52 k J/mol。硼锂溶液对裂纹扩展速率有一定的影响,其影响程度和溶液在特定温度下的pH值有关。应力腐蚀断口呈现典型的沿晶开裂形貌,且裂纹沿着大角度晶界扩展。     

激光喷丸强化对电化学充氢316L奥氏体不锈钢振动疲劳性能的影响

本文研究了激光喷丸强化对电化学充氢316L奥氏体不锈钢振动疲劳性能的影响。测试分析了不同激光功率密度喷丸316L不锈钢充氢试样的残余应力、显微硬度和微观组织结构,并对比研究其振动疲劳寿命和断口形貌。结果显示,激光喷丸诱导材料表层位错密度增加,并有效细化晶粒,抑制了氢原子的入侵,同时复杂晶界和高密度位错增殖结构阻碍了氢原子的聚集和扩散,降低了316L奥氏体不锈钢马氏体转变的程度,有助于抑制微裂纹的萌生;另一方面,激光喷丸诱导产生的高幅残余压应力,不仅抑制了氢原子的渗透,而且还提高了疲劳裂纹扩展阈值,减缓裂纹扩展速率。振动疲劳试验结果显示,激光喷丸316L不锈钢充氢试样的疲劳寿命均获得了显著提高,最大提升幅值可达79.36%,断口形貌分析进一步证明了激光喷丸可有效降低充氢试样疲劳裂纹扩展速率,提升材料断裂韧性,进而改善材料的振动疲劳特性。     

国产316LN不锈钢的室温低周疲劳行为研究

测试了国产第三代核电站一回路主管道材料-316LN不锈钢的室温低周疲劳性能,讨论了微观机理并建立了Manson-Coffin疲劳寿命模型。结果表明,随着应变幅的增大,滞回曲线宽度及峰值应力随之增大,疲劳过程中先后发生了循环硬化、快速循环软化、慢速软化和失稳四个变形阶段;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;疲劳断口由裂纹源区、扩展区和最终断裂区组成,疲劳裂纹主要萌生于表面,裂纹区具有典型的疲劳辉纹形貌,最终断裂区具有韧窝形貌。     

316L不锈钢在高温酸碱溶液中的应力腐蚀行为

采用慢应变速率拉伸实验方法,研究了高温高压水环境中pH值对316L不锈钢应力腐蚀开裂的影响规律,并通过扫描电镜对试样断口形貌进行分析。结果表明:在300℃时,316L不锈钢在酸性和碱性溶液中的应力腐蚀开裂敏感性较大,且酸性越强,敏感性越大。在中性溶液中,316L不锈钢的强度和塑性损失较小,应力腐蚀敏感性较小,断口分析与之吻合。     

反应堆冷却剂环境对690合金传热管疲劳性能影响研究

针对核电站蒸汽发生器690合金传热管,通过在室温空气、高温空气以及模拟压水堆高温高压水环境下的疲劳性能测试,研究了环境介质对690合金传热管疲劳寿命的影响,并考察了溶解氧和应变速率等的影响规律,探讨了高温高压水环境下690合金传热管的腐蚀疲劳机理。结果表明,690合金传热管具有足够的疲劳设计安全裕度,且压水堆冷却剂环境对690合金传热管的疲劳寿命影响不明显;溶解氧和应变速率对690合金传热管的腐蚀疲劳寿命的影响也不敏感。推测690合金传热管在高温高压水中的腐蚀疲劳过程主要由膜破裂滑移/溶解机制控制。     

304L不锈钢在高温高压水蒸气中的应力腐蚀开裂行为

目的 研究304L不锈钢在高温高压水蒸气中的应力腐蚀开裂行为及机理。方法 采用慢应变速率试验分别研究了304L不锈钢在常温常压水、高温高压水、高温高压水蒸气环境中的应力腐蚀开裂行为。利用SEM、三维立体显微镜和XPS，分析试样氧化后断口区域的形貌及元素分布。结果 304L不锈钢在常温常压水中的抗拉强度为730 MPa，拉伸率为94.32%。在高温高压水、高温高压水蒸气环境中的抗拉强度分别为382、379 MPa，拉伸率分别为44.98%、47.38%。304L不锈钢在三种试验环境中慢拉伸后的断口表面布满大量韧窝，断口全貌呈韧性断裂特征，高温高压水、高温高压水蒸气中试样的抗拉强度较常温常压水中明显下降。304L不锈钢在高温高压水环境和水蒸气环境中得到的XPS谱图中各结合能峰位置几乎相同，峰的相对强度因载荷的不同而发生变化。施加载荷后，在高温高压水环境中304L不锈钢表面氧化物中的Cr含量增加，而在高温高压水蒸气环境中的Cr含量略有下降。结论304L不锈钢在高温高压水和高温高压水蒸气环境中具有相似的最大抗拉强度和最大应变值。施加载荷将影响304L不锈钢氧化过程中金属元素扩散的速度，进而影响氧化产物的成分。     

喷丸强度对316不锈钢表面完整性及疲劳寿命的影响

目的阐明喷丸强度对316不锈钢疲劳寿命的影响机制。方法不同喷丸强度处理的316不锈钢试样经化学腐蚀后,利用光学显微镜观察其微观结构的变化。采用白光干涉仪、维氏显微硬度测量系统、X射线应力分析仪等,分析喷丸处理前后316不锈钢试样的表面轮廓、表面粗糙度、显微硬度以及残余应力等的变化。利用疲劳试验机测得喷丸处理前后316不锈钢试样的拉伸性能和疲劳寿命。结果喷丸处理后,试样表面粗糙度明显增加,随着喷丸强度的增大,表面粗糙度S_a由0.04μm增至6.73μm。此外,喷丸处理后,产生了从表层到材料基体的微结构梯度,随着喷丸强度的变化,表面变形层的厚度位于110～290μm之间。喷丸过程中产生了加工硬化现象,并且引入了一定深度的残余压应力层。随着喷丸强度的增大,喷丸处理试样显微硬度的最大值由356HV_(0.1)增至435HV_(0.1),残余压应力的最大值由-633 MPa增至-750 MPa。与未喷丸试样相比,喷丸处理改善了材料的力学性能和疲劳特性,喷丸试样的塑性应变幅值降低,疲劳寿命明显增加。结论喷丸处理能够有效地改善316不锈钢的综合力学性能,增加其疲劳寿命。不同强度的喷丸处理效果差异明显,在喷丸强度为0.35 mmA时,达到最优喷丸效果。     

核电用316LN奥氏体不锈钢延性断裂阈值研究

在Gleeble-1500D模拟机上对核电用316LN奥氏体不锈钢的热拉伸行为进行了研究,获得了钢在变形温度900~1200℃、应变速率0.01~1 s-1条件下拉伸变形的真应力-真应变曲线。通过Deform-3D有限元软件模拟了热拉伸过程,利用迭代法对试样颈缩后对应的真应力-真应变曲线进行修正。对试样颈缩前塑性变形部分对应的真应力-真应变数据拟合处理,得到了不同变形条件下316LN奥氏体不锈钢的硬化指数。将修正后的真应力-真应变曲线和计算得到的硬化指数导入Deform-3D软件中模拟热拉伸过程,计算得到了316LN奥氏体不锈钢热变形时的断裂阈值。     

Effects of ion irradiation on fatigue of Fe-12Cr-20Mn stainless steel for fusion reactor applications

To minimize waste disposal problems associated with the residual radioactivity of the first wall material of a fusion reactor, fast induced radioactive decay (FIRD) alloys based on the Fe-Cr-Mn system are being investigated. The objective of this research was to evaluate the effects of irradiation on cyclic strain localization and fatigue crack initiation in a FIRD Fe-12Cr-20Mn alloy and to compare the response to commercially available 316 stainless steel. The alloys were irradiated with 200 keV Fe ions to a dose of 1 x 10 ions/cm² and 15.5 keV He ions to a dose of 7 x 10¹⁵ ions/cm² to simulate the irradiation-induced defect structure and helium concentration that would be produced in a fusion reactor. Irradiated specimens were fatigued in a cantilever beam fatigue testing machine with the deflection set to produce a fully reversed total strain amplitude of 0.25% on the surface of the specimen. Acetate replicas were obtained during the fatigue tests to provide a record of surface fatigue damage. Transmission electron microscopy (TEM) analyses were performed to characterize the microstructural changes resulting from the irradiations and interactions between fatigue-induced glide dislocations and the irradiation-induced defects. Results indicate that the irradiated Fe-Cr-Mn alloy exhibits fatigue properties similar to 316 stainless steel. Glide dislocations produced by fatigue cycling annihilate irradiation-induced defects. The defect annihilation causes the formation of cleared channels in which the cyclic plastic strain is localized. Subsurface slip bands penetrate the irradiated regions through the cleared channels and serve as fatigue crack initiation sites.     

Influence of surface finish on fatigue cracking behavior of reactor pressure vessel steel in high temperature water

The low cycle fatigue behavior of a low‐alloy reactor pressure vessel (RPV) steel was investigated in high temperature water. Main attention was paid to the effects of surface finish of specimens on fatigue cracking behavior. It was found that the influence of surface finish on fatigue resistance of the steel was strain‐rate dependent in high temperature water. Pretty obvious degradation of fatigue resistance appeared at fast strain rate with rougher surface finish. At slow strain rate, surface circumferential scratches promoted crack initiation and propagation. The fracture surface showed relatively flat and slight crack‐arrest features. At fast strain rate, surface scratches also promoted crack initiation, but seemed not to dominate crack propagation. The fracture surface showed typical terraced and fan‐like features. The above fatigue cracking behavior can be rationalized by a strain‐rate dependent environmentally assisted cracking process of low‐alloy RPV steel in high temperature water.     

Evaluation of stress corrosion cracking phenomenon in an AISI type 316LN stainless steel using acoustic emission technique

This paper deals with the analysis of the acoustic emission (AE) signals to determine the micro-process during stress corrosion cracking (SCC) of AISI type 316LN stainless steel that cause the AE, and thus the mechanism of the SCC process. AE with amplitudes ranging from 27.6 to 46.5 dB with different counts, energy and rise times occurred during SCC of type 316LN stainless steel in 45% MgCl₂ at 413 K. The analysis of the AE signals in conjunction with fractography indicated that a surge in the AE counts and energy indicated initiation of SCC. AE was found to be continuous prior to the initiation. The time gap between AE events increased during initiation. AE events occurred in bursts during crack growth. Plastic deformation ahead of the crack tip was determined to be the major source of AE during propagation of SCC in type 316LN stainless steel. The cracking was found to initiate and propagate in the transgranular mode.     

Behavior of 316L stainless steel containing corrosion pits under cyclic loading

The environmental performance of 316L grade stainless steel, in the form of tensile specimens containing a single corrosion pit with various aspect ratios, under cyclic loading in aerated chloride solutions is investigated in this study. Results from environmental tests were compared and contrasted with those obtained using finite element analysis (FEA). Fractography of the failed specimens obtained from experiments revealed that fatigue crack initiation took place at the base of the shallow pit. The crack initiation shifted towards the shoulder and the mouth of the pit for pits of increasing depth. This process is well predicted by FEA, as the strain contour maps show that strain is the highest around the centric strip of the pit. However, for shallow pits, local strain is uniformly distributed around that strip but begins to concentrate more towards the shoulder and the mouth region for increasingly deep pits.     

Elektrochemische Untersuchung der Rißbildung bei Schwingungsrißkorrosion im stabil-passiven Werkstoffzustand

Electrochemical investigation of crack initiation during corrosion fatigue of stainless steels in the passive state The corrosion fatigue behaviour of three stainless steels - ferritic (12% Cr), austenitic (type 316 Ti) and austenitic-ferritic (type 31803; Duplex stainless steel) - was studied under rotating bending moments in aqueous sulphuric acid of 30°C. An instrumental set-up for recording the transient currents of specimens during potentiostatically controlled corrosion fatigue is described. Based on this transient current signal technique, three stages on the corrosion fatigue process can be discerned. In the incubation period, small stochastic current transients are caused by the response of the passive layer to alternating stresses and environmental conditions. The appearance of sinusoidal current signals indicates crack initiation whereas the phase angle between a fixed marker - i.e. a light barrier signal -, and the anodic amplitude represents the site of initiating cracks. Finally, the crack growth period is characterized by an increasing cell current and steadily growing sinusoidal current signals caused by the interplay of microplastic and repassivation processes at the crack tip.     

Effect of friction stir and activated-GTA welding processes on the 9Cr–1Mo steel to 316LN stainless steel dissimilar weld joints

ABSTRACT

The consequence of friction stir welding (FSW) and activated-gas tungsten arc welding (A-GTAW) processes on the evolution of microstructure and mechanical properties of 9Cr–1Mo (P9) steel to 316LN stainless steel dissimilar weld joint is investigated. The FSW specimen shows considerably higher tensile strength (～652?MPa) compared to A-GTAW specimen (～595?MPa) as well as its base metal of P9 (～642?MPa) and 316LN (～608?MPa) owing to the formation of tempered martensite and refined austenite in P9 and 316LN weld portion, respectively. The cross-weld tensile test revealed that the specimens failed in the base metal of 316LN SS for both FSW and A-GTAW process with ductile mode fracture. This study proves that FSW could be an alternate joining technique.     

CORROSION FATIGUE CRACK INITIATION BEHAVIOR OF 316L STAINLESS STEEL IN HANK’S SOLUTION

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选区激光熔化316L不锈钢的各向组织与性能

对采用选区激光熔化(SLM)制备的316L不锈钢增材制造试样进行了横向、纵向力学性能与微观组织分析。结果表明,增材制造SLM试件亚结构组织由尺寸为0.4 μm左右的胞状组织所构成,组织之间无明显的成分偏析,纵向与横向拉伸强度分别达到808和713 MPa,在经过1050 ℃热处理后,原组织中部分胞状组织消失,纵向及横向强度分别下降到673 MPa及579 MPa,增材制造试样相对传统热轧试样(550 MPa)具有明显的强度优势。SLM试样组织中存在未熔合缺陷,缺陷几何形状的方向性对其在拉应力作用下连接成裂纹有显著影响。热处理后缺陷长度方向与拉伸应力平行的纵向试样伸长率达到47.5%,横向试样伸长率为20%,伸长率指标均显著低于热轧316L钢试样,未熔合缺陷是导致3D打印试件塑性指标降低的主要因素之一。