注铌法改善铀及铀铌合金抗蚀性的研究

利用离子注入表面优化技术,在贫铀及铀铌合金基体上进行了离子注入铌表面改性处理,并主性层元素的分布、化学急及耐腐蚀性能进行了分析和测试。实验结果表明,离子洲主铌可不同程度地提高贫铀及Ｕ－Ｎｂ（１）全合的抗电化学腐蚀、水汽腐蚀及热氧化腐蚀能力。最后讨论了注铌改性腐蚀性提高的原因。     

热处理和铌含量对铀铌合金显微组织与相结构的影响

铀铌合金的显微组织和相结构与铌含量和热处理制度密切相关。通过定量金相法对不同热处理制度下铀铌合金的显微组织和相结构演化进行了表征和分析。结果表明:淬火铀铌合金为单相过饱和固溶体,随铌含量增加,其相结构变化依次为正交、单斜、四方结构,显微组织形貌变化依次为针状、板条、等轴晶粒;慢冷铀铌合金为富铌(γ_(1-2))和贫铌(α′)片层交替组成的珠光体;马氏体组织退火时优先沿奥氏体晶界发生胞状分解,分解组织也为富铌和贫铌片层交替组成的珠光体,分解动力学符合JMAK方程。     

注铌法改善纯铁的抗腐蚀性研究

离子注入法能解决一些传统表面处理工艺所不能解决的问题,并在一些材料上得到了成功应用。为了研究其在核材料和昂贵材料上应用的可能性,利用离子注入表面化技术,在纯铁基体上进行了离子注入铌表面改性处理,并改性层元素的分布、化学态及耐腐蚀性能进行了分析和测试。实验结果表明,离子注入铌可不同程度地提高纯铁的抗电化学腐蚀、水汽腐蚀及热氧化腐蚀能力,最后讨论了注铌改性层耐蚀性提高的原因。     

铀表面纳米铌镀层的结构及其抗腐蚀性能

铌镀层硬度高,化学稳定性好,抗大气腐蚀性能优良,与铀的热膨胀系数接近,可作为铀的防腐蚀镀层,过去对该镀层结构研究不够.为此,采用磁控溅射离子镀技术在贫铀表面以不同偏压制备了铌镀层,利用X射线衍射仪和扫描电镜对镀层的组织结构进行了表征,利用电化学测试技术对铀表面铌镀层在含50 μg Cl~-的KCl水溶液中的抗腐蚀性能进行了研究.结果表明:铌镀层平整致密,但存在靶材飞溅颗粒形成的镀层缺陷,铌镀层为bcc结构,存在择优取向与晶粒细化等特性,为纳米层;在含50μg/g Cl~-的KCl溶液中,金属铌的腐蚀电位-138.5mV高于贫铀的腐蚀电位-641.2 mV,铌镀层对贫铀是一种阴极性镀层,对贫铀的保护基于其对腐蚀介质的物理屏障作用;镀铌贫铀样品的极化电阻和电化学阻抗幅值远大于贫铀,腐蚀电流远小于贫铀,铌镀层对贫铀基体具有良好的腐蚀防护作用.     

温度对40Cr13钢等离子表面渗铌层组织的影响

为提高马氏体不锈钢的耐蚀和耐磨性能,选择40Cr13不锈钢为基材、纯铌板为靶材,采用双辉等离子表面冶金技术在不锈钢表面制备合金化层.用SEM、GDOES、XRD等方法分析渗铌温度对铌合金层组织、成分、相组成、表面形貌及硬度的影响,并对渗层形成机制及表面硬化机理进行了研究.结果表明:在900~1 000℃形成的铌合金层组织均匀致密,合金层主要由Nb2C、Nb C、Fe2Nb、Cr2Nb及铌组成;合金层表面粗糙度随渗铌温度的提高而增加;合金层厚度随渗铌温度改变发生不同变化规律,950℃渗铌形成的渗层约13μm,900和1 000℃渗铌后合金层厚度均为7μm左右;不同温度渗铌后试样的表面硬度与基体相比均有较大幅度的提高,1 000℃渗铌后试样表面硬度高达约985 HV0.025,900℃渗铌后约758 HV0.025,而950℃渗铌后表面硬度最低,约698 HV0.025.     

合金化对铌-硅基超高温合金组织和性能影响的研究进展

综述了合金化元素对铌-硅基超高温合金组成相、相结构以及组织形貌的影响规律,并讨论了合金化元素在相形成方面的作用机理;总结了几个重要合金化元素对铌-硅基合金高温抗氧化性能和力学性能的影响规律;最后介绍了相图计算在铌-硅基合金成分设计和组织分析方面的应用.     

铌合金表面渗镀复合涂层及其抗氧化研究

利用包埋渗结合化学镀技术在铌合金表面制备了复合涂层,研究了涂层在退火过程中的元素扩散行为及涂层的高温抗氧化性能。结果表明:复合涂层以晶态Ni和Al_3Nb相为主;退火过程中渗层中的Al元素向外扩散,涂层转变为晶态,形成了Ni Al_3、Al_3Nb、Ni Al相。对退火前后的涂层进行1000℃恒温氧化实验,20 h后沉积态涂层的增重为7.7 mg/cm~2,表面主要含Ni O、Al_2O_3、Ni Al相;退火态涂层样品的增重为4.9 mg/cm~2,表面生成了Al_2O_3、NiNb_2O_6、NiAl_2O_4等相。氧化后涂层与基体结合良好。退火态涂层表面由于富Al元素,氧化后形成较多的Al_2O_3,比沉积态的涂层能更有效地减缓氧化进程,提高铌合金的抗氧化性。     

超高真空磁控溅射法沉积铀薄膜及其表面状态

铀薄膜有助于原子参数的测试研究,目前对铀薄膜研究的报道较少.利用超高真空磁控溅射法在单晶Si片上制备了铀薄膜.通过扫描电子显微镜(SEM)对铀薄膜的表面形貌进行了观察,利用X射线光电子能谱仪(XPS)及X射线衍射仪(XRD)对铀薄膜的表面结构及元素状态进行了分析和表征.结果表明:铀薄膜呈片状式生长,比较致密、连续,表面由铀及氧化铀组成,之下为纯铀.     

铀铌合金结构及性能调控研究进展

铀铌合金作为一种重要的核工程材料,因其较高的密度、优异的耐蚀性能和良好的力学性能等特点,被广泛应用于核工业领域。铀铌合金受成分及热处理工艺影响显著,表现出复杂的相转变和组织结构特征,使得铀铌合金耐腐蚀性能及力学性能可在较大范围内获得调控。本文按照"成分/工艺-结构-性能"主线,综述了近年铀铌合金在结构、性能调控方面的研究进展,认为:低温时效机制和杂质控制技术仍是铀铌二元合金研究中需要重点关注的问题;高通量设计、制备及表征手段的出现,为未来铀铌多元合金结构及性能调控研究带来了新的机遇与挑战。     

1Cr13不锈钢电火花表面强化层摩擦磨损性能研究

针对我国水轮机过流部件磨蚀严重这一问题,选用WC电极对水轮机叶片用1Cr13不锈钢材料进行电火花表面强化处理,对生成的强化层摩擦磨损性能进行了深入研究,并利用扫描电子显微镜和X射线衍射仪对强化层的金相组织、元素分布以及相结构进行了分析.结果表明,强化层的硬度和耐磨性明显高于工件基体,强化层的硬度在白亮层最高,而在强化层...     

Effect of strain rate on fracture of U-5.5Nb alloy

The microstructure and tensile properties of an aged U-5.5?wt-% Nb alloy have been experimentally investigated with the aim of obtaining the influence of strain rates on fracture behaviour. The result shows that strain to failure is sensitive to strain rate and decreases with an increase in the strain rate. Fracture surface analysis indicates that the alloy exhibits a typical ductile fracture. Two types of carbides (niobium carbide and uranium carbide), mainly distributed at the grain boundary, are confirmed, which participate in the process of fracture and are involved in different void nucleation mechanisms during the final ductility fracture. Namely, niobium carbide tends to generate voids by debonding with the matrix, while uranium carbide is more likely to experience cracking.     

Exposure of workers in a mineral processing industry in Brazil

In Brazil there are many regions where the extraction mining and processing of ores containing elements of great economical importance as tin, niobium and tantalum. Some of these ores have uranium and thorium natural decay series associated. This study was carried out in a niobium mine, where is obtained concentrates of niobates-tantalates, cassiterite and zirconite. The aim of this study is the evaluation of the occupational exposure to uranium, thorium, niobium and tin through urine bioassay data. In order to have it, 105 urine samples were analysed: 17 samples of exposed workers collected after a working day, 49 samples of exposed workers collected before a working day and 39 samples of local non-exposed people, assigned as a control group. The samples were analysed by mass spectrometry. The obtained results showed that the average concentration of Nb, Sn and U in the exposed group is statistically higher than those found in the control group indicating an occupational exposure. For Th there were no statistically difference between the exposed and the control group.     

Study on double-glow plasma niobium surface alloying of pure titanium

A niobium modified layer on a pure titanium surface was obtained by means of a double-glow plasma surface alloying technique. Microstructure and phases resident in the alloy layer were analyzed. The processing parameters and effects of cathode sputtering before the diffusion process were also studied. The results show that the surface niobium content in the modified layer is similar to that in the Ti-45Nb alloy, and decreases gradually from the surface into the underlying substrate. The oxidation behavior of the modified pure titanium at 900 °C was noticeably improved after the niobium alloying process. Characterization was performed using X-ray diffraction (XRD) and scanning electron microscopy (SEM). The oxidation mechanism is also discussed.     

干摩擦对金属材料亚表层微观结构的影响

滑动摩擦可以产生极高的应变和应变率,导致金属表层强烈塑性变形。经过摩擦处理后,纯铜、纯铌表层均发生严重塑性变形。纯铜塑性变形层厚度200—4001μm之间,变形层深度随载荷、速率升高而增加,在200cycles即接近饱和。变形层沿深度方向呈梯度变化分布,其亚表层呈梯度结构,分别为塑性流动层、变形层和基体,最表层晶粒尺寸达到纳米量级。纯铌经过摩擦处理后,磨损量较大,表面较粗糙,且亚表层变形不太均匀。     

Effect of process parameters and niobium carbide addition on microstructure and wear resistance of laser cladding nickel-based alloy coatings

Based on the background of the engineering application of automobile mold repair and surface strengthening, the effects of process parameters on the formation and microstructure of laser cladding nickel(Ni)-based alloy coating were studied. The optimal parameters were: laser power 2000 W, powder feeding rate 15 g/min, scanning speed 4 mm/s. Under this process, the cladding layer and the substrate can exhibit good metallurgical bonding, and the cladding layer has fine crystal grains and a low dilution ratio. On this basis, different mass fractions of niobium carbide (NbC) powder were added to the nickel-based powder and laser cladding was carried out on the surface of die steel. The phase composition, microstructure, hardness and wear resistance of the coating were studied. The results show that with the increasing of niobium carbide addition, the hardness of the cladding layer decreases, and the wear loss of the cladding layer decreases first and then increases. When the niobium carbide addition reaches 6 wt.%, the wear loss of the cladding layer is the least, and the wear resistance is the best.     

Laser polishing for topography management of accelerator cavity surfaces

Improved energy efficiency and reduced cost are greatly desired for advanced particle accelerators. Progress toward these goals can be made by atomically‐smoothing the interior surface of the niobium superconducting radiofrequency (SRF) accelerator cavities at the heart of these machines. Laser polishing offers a green alternative to the present aggressive chemical processes. We found parameters suitable for polishing niobium in all surface conditions that are expected for cavity production. Careful measurement of the resulting surface chemistry revealed a modest thinning of the surface oxide layer, but no contamination.     

低应变率下形变对亚共析U-Nb合金微观组织结构的影响

摘要对亚共析U-Nb合金进行了不同形变量和不同拉伸速率的静态拉伸实验，利用光学显微镜、扫描电镜、X射线衍射仪和透射电镜分析了形变前后亚共析U-Nb合金微观组织结构的变化。结果表明：在低应变率范围内（10^-5～10^-2/s），亚共析U-Nb合金在形变过程中，其变形表面出现浮凸，随着形变量的增加，浮凸台阶增多。内部的孪晶马氏体相互合并长大并发生择优取向为亚共析U-Nb合金变形初期的主要变形机制。     

铀表面脉冲辉光等离子氮化初步研究

采用脉冲辉光等离子体离子氮化技术对贫铀表面进行了氮化处理,采用俄歇电子能谱(AES)对氮化层进行元素深度剖析,采用X射线衍射(XRD)、扫描电子显微镜(SEM)对氮化层组织结构进行了分析表征。结果表明:脉冲偏压-900 V,工作氮分压50 Pa、100 Pa,氮化时间2.5 h~4 h下在贫铀表面能获得约20μm厚的氮化层,氮化层为U2N3的单一立方结构且均匀致密,脉冲辉光等离子氮化技术能在贫铀表面实现氮化。     

Mineral processing in the Indian nuclear energy programme

Uranium is the basic raw material for a nuclear energy programme. Uranium ore is processed in India by the well-known method of sulphuric acid, ion-exchange concentration and its final precipitation as magnesium diuranate—‘yellow cake’. We have established a process for uranium recovery from the tailings of copper concentrators which also enables recovery of small amounts of copper, nickel and molybdenum present in the uranium ore. Another major activity of this centre has been the exploitation of mineral-rich beach sands to produce ilmenite, rutile, zircon and monazite. Downstream industries have also been established for chemical processing of these minerals. Production of niobium from low-grade ores and beryllium from beryl ore is also being carried out on a moderate scale.