辐照温度对SUS316L不锈钢中二次缺陷及肿胀的影响

利用超高压电子显微镜分别在350、400、450以及500 ℃下对SUS316L奥氏体不锈钢进行剂量为3.6 dpa的电子束辐照,通过观察和分析辐照后样品中的空洞和位错环数量密度以及肿胀率,讨论了不同温度下电子束辐照对材料肿胀率的影响。结果表明,不同温度下,样品中都产生二次缺陷,如位错环和空洞;空洞引起辐照肿胀;在350～450 ℃范围内,肿胀率随着温度升高而增加,并在450 ℃达到最高;450 ℃后,肿胀率降低。不同温度下,两种二次缺陷对于点缺陷的尾闾强度不同,肿胀率与位错环、空洞在显微组织中所占比例有关。试验研究辐照肿胀率与二次缺陷间的关系,为进一步理解辐照肿胀机理、寻求抑制辐照肿胀的方法提供依据。     

脉冲激光亦或电子束辐照对SUS316 L奥氏体不锈钢中空位扩散的影响

利用激光-超高压电子显微镜系统在500℃对SUS316L奥氏体不锈钢进行了电子束辐照和脉冲激光-电子束双束同时辐照(以下简称:同时辐照),通过观察和分析辐照后自由晶界处无空洞区域以及元素偏析,以电子束辐照结果为标准,对比研究了同时辐照对空位扩散的影响.结果表明:同时辐照后的无空洞区域宽度为48 ±16 nm,小于电子辐照的71 ±27 nm;不论在偏析程度还是偏析宽度上,同时辐照条件下Cr和Ni的偏析都小于对应的电子束辐照;同时辐照下空位的扩散通量仅为电子束辐照的45.7%.通过分析得出,和电子辐照相比,同时辐照促进了空位与间隙原子的再结合,限制空位向尾闾扩散,进而造成流入尾闾的空位数量减少,极大地抑制了辐照偏析与肿胀.脉冲激光-电子束双束同时辐照可以为探索抑制肿胀方法提供新的思路.      

电子辐照对9Cr- ODS钢中氧化物稳定性的影响

利用超高压电子显微镜系统在450、500和550 ℃下对9Cr- ODS铁素体/马氏体钢（F/M钢）进行了电子束辐照，通过观察和分析辐照前后钢中Y- Ti- O纳米氧化物的形貌及成分变化，对比研究不同温度下电子辐照对氧化物稳定性的影响。结果表明，不同温度下，电子辐照后的氧化物尺寸发生了不同程度的减小现象。辐照前后氧化物尺寸减小率分别为8.51%（450 ℃）、19.38%（500 ℃）和25.99%（550 ℃）；氧化物内铬成分变化程度关系为550 ℃＞500 ℃＞450 ℃。通过分析得出，电子辐照条件下，钢中Y- Ti- O弥散氧化物抑制了材料的辐照肿胀。高能电子轰击以及辐照中产生的过饱和点缺陷的扩散会促使氧化物中溶质原子移动，从而造成了氧化物尺寸的减小。温度的增加提高了空位的扩散速率，加速了氧化物尺寸的减小。研究9Cr- ODS钢在电子辐照下的损伤行为有助于探究氧化物辐照损伤机理，为后期控制和减少9Cr- ODS钢辐照损伤现象提供依据。     

材料辐照损伤中的点缺陷团簇与一维迁移现象

材料辐照损伤是核反应堆材料、尤其是核聚变堆材料所面临的重要问题。高能粒子（中子、离子、电子）辐照在材料中会产生大量的点缺陷,即自间隙原子和空位。这些点缺陷聚集在一起会形成自间隙原子团簇和空位团簇,从而对材料结构和性能的演化产生重要影响。空位团簇包括有空洞、层错四面体、空位型位错环,而自间隙原子团簇则只有自间隙型位错环。本文介绍了两种点缺陷团簇的性质、及其对于以材料辐照肿胀为主要内容的材料辐照损伤性能的影响。作为空位团簇,比较详细介绍了具有本课题组特色的空位型位错环的研究,同时分析了合金元素和氢同位素对空位型位错环的影响。在铁试样中形成的这种空位型位错环尺寸可达100 nm左右,该空位型位错环具有两种柏氏矢量, b =<100> 和 b =1/2<111>,前者的数密度比后者高一个数量级。对于自间隙原子团簇,则重点介绍了与其相关的一维迁移现象及其研究动态,该一维迁移性能有可能是影响高熵合金辐照性能的重要因素。      

电子辐照对直拉硅单晶电学参数的影响

对N型[111]晶向直拉硅样品进行电子辐照,然后在不同温度下进行常规热处理,对比研究了不同辐照剂量的样品少子寿命和电阻率随退火温度的变化。结果表明:直拉硅单晶样品经电子辐照后电阻率增加,少子寿命下降,辐照剂量越高电阻率增加的越多,少子寿命下降越明显。对辐照样品进行不同温度热处理发现热处理温度低于600℃,少子寿命基本处于稳定值,当退火温度达到650℃时,辐照样品的电阻率与少子寿命均恢复至辐照前的初始值,表明在该温度下辐照引入的缺陷基本消除,因此晶体的导电能力逐渐恢复。而经750℃热处理后,辐照样品的少子寿命和电阻率分别出现一个低谷,辐照剂量越高电阻率和少子寿命值在该温度下下降幅度越大,而且随着热处理时间的延长,辐照样品电阻率不断下降,通过间隙氧含量的测量也初步证明电阻率的下降与间隙氧原子的偏聚有关,该温度下电阻率的下降与辐照相关联。     

探究热处理工艺对SUS301不锈钢硬度的影响

研究了热处理工艺保温的温度和时间对奥氏体不锈钢SUS301试样硬度的影响。探究试样在不同保温温度、相同保温时间下和在相同保温温度、不同的保温时间两种条件下,热处理后水冷试样硬度的变化,发现热处理温度在500℃之前,SUS301不锈钢由于在冷却过程中产生残余应力硬度会略微增加;500℃之后奥氏体不锈钢由于固溶作用,应力得以释放,硬度显著下降;热处理温度相同,增加热处理时间,SUS301不锈钢的硬度略微下降。     

核电承压设备用钢SA738Gr.B的离子辐照性能

通过理论计算确定氢离子辐照下武钢产SA738Gr.B钢位移损伤峰值的深度,对不同剂量辐照(0.2、0.5、1.0dpa)前后微观组织的特征和元素分布情况进行分析,判定离子辐照对SA738Gr.B钢的显微组织的影响.结果表明,通过高倍TEM观察以及STEM技术的分析,在SA738Gr.B钢基体中并未发现氢泡和大尺寸空位团,氢离子辐照下材料肿胀很小.通过对比0.5 dpa位移损伤量的微观组织与1.0 dpa位移损伤量的微观组织,可以明显看出,位移损伤量低的SA738Gr.B钢中的位错密度、位错环数量都大大降低.随着辐照剂量的提高,钢中位错密度和位错环数逐步增多,可以初步判定钢的辐照硬化效应程度.     

碳离子辐照对纯钨组织结构及表面硬度的影响

采用扫描电子显微镜、透射电子显微镜及纳米压痕仪研究了700℃下碳离子辐照对钨的表面形貌、组织结构和表面硬度的影响。结果表明,碳离子辐照会导致样品表面出现辐照蚀坑,且随着辐照剂量的增加,辐照蚀坑尺寸变大。碳离子辐照在样品内部产生了大量位错环,且随辐照剂量增加,位错环数密度和尺寸均增大。碳离子辐照使钨表面发生严重的辐照硬化效应,样品表面硬度随辐照剂量增加明显增大。当辐照剂量达到8.0 dpa时,钨表面平均硬度达到15.85 GPa。辐照产生的位错环是辐照硬化的主要原因。     

再加热温度对含Nb，Ti钢第二相粒子固溶及晶粒长大的影响

 通过热力学计算和萃取复型分析技术,对高Ti含Nb钢中第二相粒子在不同加热温度下的固溶情况和奥氏体晶粒的长大规律进行了研究。结果表明：再加热温度低于1 180 ℃时,钢中Nb、Ti含量随温度升高显著增加。Nb、Ti固溶量分别在1 210 ℃和1 180 ℃以上趋于稳定;再加热温度在800~1 100 ℃时,以尺寸小于30 nm、分布较均匀的小粒子为主,呈球形,奥氏体晶粒尺寸在30 μm以下。再加热温度在1 180~1 210 ℃时,第二相粒子数量减少,尺寸多在100~200 nm之间,形态多为立方形和球形,奥氏体晶粒尺寸略微增加。随着再加热温度的进一步升高,析出粒子数量迅速下降,尺寸多为大于200 nm的方形粒子,此时奥氏体晶粒迅速长大至100 μm以上;析出粒子组成均为Nb、Ti复合的碳氮化物,其Nb/Ti原子比随温度升高而降低;试验钢的晶粒粗化温度为1 210 ℃,确定实际加热温度为1 180~1 210 ℃。     

基于渗碳体调控低合金钢中块状逆变奥氏体与奥氏体晶粒尺寸

逆变奥氏体微观组织显著影响钢铁材料的最终组织性能,阐明块状奥氏体的形成规律对于精准掌握逆相变至关重要。本文以Fe–2.5Mn–1.5Si–0.35C合金为研究对象,通过OM、SEM和EBSD等手段研究了不同预回火条件下晶内块状奥氏体与最终奥氏体晶粒尺寸的演变规律。研究结果表明,随预回火温度自350 ℃升高至650 ℃,晶内块状奥氏体体积分数呈现出先增加后迅速降低的趋势;400 ℃预回火条件下,随预回火时间的延长,晶内块状奥氏体体积分数先增加后趋于稳定;预回火促使晶内块状奥氏体形成,导致最终奥氏体晶粒显著细化。随着预回火温度的升高,逆相变前渗碳体发生粗化,增加了晶内块状奥氏体的有效形核位点,此促进了晶内块状奥氏体的形成。此外,晶内块状奥氏体具有多重取向,晶内块状奥氏体的增加,使得逆相变后奥氏体晶粒显著细化。本研究提供了一种在不改变钢化学成分的条件下,通过控制渗碳体实现对逆相变晶内块状奥氏体形成和最终奥氏体晶粒尺寸调控的新方法。      

Dynamic Recrystallization Behavior and Microstructure Evolution of AISI 304N Stainless Steel

Dynamic recrystallization of 304N stainless steel was investigated at deformation temperatures of 900–1300 °C and strain rates of 0.01–10 s^?1 by a Gleeble-1500 thermo-mechanical simulator. And the microstructure evolutions of specimens with different deformation temperatures were observed by using a transmission electron microscope. Results indicated that compared with conventional AISI 304 austenitic stainless steel, 304N stainless steel has higher deformation resistance force and deformation activation energy under similar conditions. In addition, the flow stress constitutive equation of 304 N stainless steel was obtained by regression analysis of experimental stress-strain data, and the calculated values proposed by the mathematical model agree well with the experimental results.     

M23C6析出相对节镍型奥氏体不锈钢冷轧表面裂纹的影响

为找出生产的节镍型奥氏体不锈钢冷卷表面裂纹形成原因,通过光学显微镜、扫描电镜对表面裂纹进行检测分析并结合热处理试验及热力学软件JMatPro进行分析计算研究。检测分析发现裂纹处晶界存在大量的析出相,据此推测析出相是导致钢材冷轧形成表面裂纹的主要原因。模拟连续退火工艺开展热处理试验,结果表明正常退火工艺无法完全消除热轧工序钢卷晶界处聚集的大量析出相。计算研究该成分体系下奥氏体不锈钢的平衡相图,结合能谱及透射电镜衍射斑点分析,结果表明M₂₃C₆碳化物的沉淀温度范围为500～925 ℃,钢卷从高温缓慢冷却下来会析出M₂₃C₆碳化物,析出鼻温区为850～900 ℃。以此结合实际工艺流程对减少钢卷中M₂₃C₆碳化物析出提出了可能的措施。     

A study of void formation in fast neutron-irradiated metals

Experimental observations on the temperature dependence of void formation in Type 304 stainless steel are presented. The average void size is seen to increase while the void number density decreases with increasing irradiation temperature. The total void volume reaches a maximum at an intermediate temperature (～500°C). A thermodynamically based model for void formation has been developed in an effort to understand these and other experimental observations. The model is a quasi-steady-state approach that attempts to describe the void and dislocation loop nucleation and growth rates as a function of temperature, neutron flux, and type and density of point-defect sinks. The model was written in the form of a computer routine which iterates over small time steps and fitted to experimental observations of void formation in irradiated austenitic stainless steel by adjustment of material constants within reasonable limits. Good agreement was obtained for a wide range of experimental results. Development of the model has emphasized that some kind of preferential attraction between one type of sink and one type of point defect is necessary in order for void growth to occur. The preferential attraction suggested is that between the stress field of a dislocation and the misfit strain of an interstitial. The model also pointed out the necessity of separating the neutron flux and time of irradiation when reporting information on void formation. It is expected that quite different dependences of void size and number density on the total neutron dose would be obtained depending on whether the experimental information was obtained under constant flux or under constant time conditions. It was also concluded that the magnitude and temperature dependence of dislocation loop formation would have a marked effect on void formation.     

形变强化和逆相变细晶强化对Fe-18Cr-8Ni钢组织和性能的影响北大核心CSCD

奥氏体不锈钢较低的屈服强度限制了它在结构件中的使用。采用形变和相逆转变方法分别制备出了高屈服强度的奥氏体不锈钢。利用X射线衍射仪、光学显微镜、扫描电子显微镜、透射电子显微镜、电子背散射衍射技术和万能试验机分别对奥氏体钢进行组织表征和力学性能测试,结果表明粗大的奥氏体晶粒在形变过程中形成位错、剪切带、应变诱导马氏体等组织,相逆转变方法获得了超细的无缺陷等轴奥氏体晶粒。形变强化和细晶强化均能明显提高奥氏体不锈钢屈服强度(280 MPa提升至550 MPa)的同时保持较好的塑性(伸长率46%和55%)。     

5%Si高硅奥氏体不锈钢元素偏析及均匀化处理

 高硅奥氏体不锈钢由于高含量硅元素的加入使其具有优异的耐高温腐蚀性能和较低的成本,在制酸行业有着潜在的应用价值。然而,该合金中高含量硅元素的加入会促进凝固过程中溶质再分配,进而造成显著的元素偏析,最终导致合金内部产生枝晶组织和大量的有害相。对铸锭组织进行均匀化处理能够有效消除枝晶与元素偏析,促进析出相回溶和枝晶消融,从而改善材料的热塑性,有效应对热变形开裂问题。因此,采用金相显微镜(OM)、扫描电镜能谱分析(SEM/EDS)、电子探针(EPMA)、JMatPro软件计算等方法,研究了实验室条件下制备的5%Si高硅奥氏体不锈钢铸锭的显微组织和元素分布状态,通过残余偏析指数、扩散动力学计算并结合均匀化处理试验验证,最终确定了5%Si高硅奥氏体不锈钢合理的均匀化处理工艺。结果表明,5%Si高硅奥氏体不锈钢凝固过程中钼元素偏析最为严重,通过残余偏析指数模型计算得到的均匀化动力学方程可用来指导该成分合金的均匀化处理工艺;5%Si高硅奥氏体不锈钢经过1 150 ℃×12 h均匀化处理后,铸锭内枝晶消融,元素偏析基本消除,析出相与铁素体回溶到基体中,合金转变为全奥氏体组织,热塑性得到改善;当加热温度达到1 250 ℃时,合金出现过烧现象,晶界开始熔化。     

Effect of oxygen on vacancy cluster morphology in metals

The extensive literature on oxygen chemisorption and solubility in metals is briefly reviewed, with special emphasis on the reduction of surface tension associated with oxygen adsorption. A thermodynamic model based on the adsorption equations of Gibbs and Langmuir is developed to determine the relative stability in the presence of oxygen of the void compared to the dislocation loop and stacking fault tetrahedron. Representative calculations are performed for copper, nickel, and austenitic stainless steel. Atomistic and elastic continuum calculations predict that void formation should not occur in most pure face-centered cubic metals during quenching or irradiation. However, the thermodynamic model predicts that oxygen concentrations of 30 to 1000 appm will stabilize void formation in copper, nickel, and stainless steel. Foils of copper and several Fe-Cr-Ni stainless steels containing various amounts of oxygen have been examined with electron microscopy following ion bombardment. The presence of 30 to 1000 appm O resulted in significant amounts of void formation, whereas no voids were observed in low-oxygen specimens, in agreement with the model predictions. Oxygen introduced by ion implantation was more effective in promoting void formation than residual oxygen. Solutes such as phosphorus in stainless steel reduced the effectiveness of oxygen as a void-stabilizing agent. This paper is based on a presentation made in the symposium “Irradiation-Enhanced Materials Science and Engineering” presented as part of the ASM INTERNATIONAL 75th Anniversary celebration at the 1988 World Materials Congress in Chicago, IL, September 25–29, 1988, under the auspices of the Nuclear Materials Committee of TMS-AIME and ASM-MSD     

Effect of oxygen on vacancy cluster morphology in metals

The extensive literature on oxygen chemisorption and solubility in metals is briefly reviewed, with special emphasis on the reduction of surface tension associated with oxygen adsorption. A thermodynamic model based on the adsorption equations of Gibbs and Langmuir is developed to determine the relative stability in the presence of oxygen of the void compared to the dislocation loop and stacking fault tetrahedron. Representative calculations are performed for copper, nickel, and austenitic stainless steel. Atomistic and elastic continuum calculations predict that void formation should not occur in most pure face-centered cubic metals during quenching or irradiation. However, the thermodynamic model predicts that oxygen concentrations of 30 to 1000 appm will stabilize void formation in copper, nickel, and stainless steel. Foils of copper and several Fe-Cr-Ni stainless steels containing various amounts of oxygen have been examined with electron microscopy following ion bombardment. The presence of 30 to 1000 appm O resulted in significant amounts of void formation, whereas no voids were observed in low-oxygen specimens, in agreement with the model predictions. Oxygen introduced by ion implantation was more effective in promoting void formation than residual oxygen. Solutes such as phosphorus in stainless steel reduced the effectiveness of oxygen as a void-stabilizing agent. This paper is based on a presentation made in the symposium “Irradiation-Enhanced Materials Science and Engineering” presented as part of the ASM INTERNATIONAL 75th Anniversary celebration at the 1988 World Materials Congress in Chicago, IL, September 25–29, 1988, under the auspices of the Nuclear Materials Committee of TMS-AIME and ASM-MSD