离子束辐照的碳纳米管及其物性研究

离子束辐照通常被认为导致材料产生缺陷, 形成无序结构, 从而破坏材料的性能。 但是, 最近利用离子束辐照碳纳米管的实验显示离子束辐照碳纳米管形成无定形的过程不能用传统的离子束辐照材料的机制来解释, 离子束辐照可导致碳纳米管形成一些自组装结构, 如无定形碳纳米结和碳纳米管连接结等。 研究还发现离子束辐照的碳纳米管薄膜在导电性和场发射性能方面都能得到明显的增强。 Ion beam irradiation is usually thought to induce defects and disordered structures in materials and then to destroy the properties of the materials. However, our recent experiments about the ion beam irradiation on carbon nanotubes(CNTs) indicate that the ion beam modification mechanism of CNTs is completely different from traditional one of bulk materials, and ion beam irradiation can lead to self organized structures in CNTs, such as amorphous junctions and CNT junctions. Moreover, the irradiated CNTs exhibit a improved conductivity and an enhanced field emission.     

利用HIRFL高能重离子束的核能材料辐照损伤研究

载能重离子与高能中子在材料中能够产生相似的级联碰撞损伤,加之重离子具有大的离位损伤截面和在材料样品中低的感生放射性,载能重离子束成为模拟先进核能装置内部结构材料辐照损伤的重要手段。HIRFL能区的重离子在结构材料中的射程一般远大于晶粒尺寸,因此能够产生材料体损伤,借助小样品技术可以获得材料力学性能变化（尤其辐照脆化）的有用信息,为探讨材料辐照损伤微结构和宏观力学性能变化的关联提供了重要条件。本文简要介绍了近年来我们基于HIRFL高能离子束开展的聚变堆候选材料辐照损伤的研究,包括低活化钢的辐照脆化行为、氧化物弥散强化（ODS）铁素体钢的结构优化对于抗辐照性能的影响、不同载能粒子辐照条件下铁素体/马氏体钢的辐照肿胀数据的关联,以及高能重离子辐照的钨材料中氢同位素的滞留行为。研究表明,结合特殊的测试技术及数据分析方法,高能重离子可作为核能结构材料辐照损伤研究及评估的有效手段。Because of the similarity in cascade damage structure in materials produced by energetic heavy ions and by fast neutrons, and the high displacement rate and low induced radioactivity of samples by heavy ions, heavy ion beam becomes an important tool to simulate radiation damage by energetic neutrons in materials in advanced nuclear energy systems. The ranges of heavy ions provided by HIRFL (Heavy Ion Research Facility in Lanzhou) are generally much larger than the mean dimensions of grains in alloys candidate to advanced nuclear reactors, and is capable of producing radiation damage in bulk scale. It therefore makes possible the evaluation of change of mechanical properties including the radiation induced embrittlement from the irradiated specimens by using miniaturized specimen techniques. In the present paper, we provide an introduction of our recent studies of radiation damage of materials candidate to future fusion reactors by utilizing heavy ion beams in HIRFL.The studies include issues as follows:ductility loss of RAFM steels causes by high-energy Ne ions, impact of oxide dispersoids on the radiation resistance of ODS ferritic steels, correlation of void swelling of ferritic/martensitic steels under different particle irradiation, and behavior of deuterium retention in tungsten under irradiation with high-energy heavy ions. The results show that high-energy heavy ions can be used as a tool to efficiently investigate or evaluate radiation damage in structure materials if combined with some special test techniques and data analysis.     

加速器-电子显微镜联机进行材料科学研究的新进展

离子或电子辐照引起的材料微结构演变是一个非常复杂的过程.用加速器 电子显微镜联机装置可原位观察载能离子束辐照及辐照后退火引起的材料微结构演变,并确定相应的辐照条件.介绍了近10年来国际上利用加速器 电子显微镜联机装置开展材料科学研究的最新进展.Ion beam or electron beam irradiation will lead to the change of material microstructure. By the use of facilities composed of an electron microscope and ion accelerator(s), the microstructure evolvement in material can be in situ studied during the irradiation and following annealing processes. The facilities have been widely used to study many kinds of materials, e.g. metal, alloy, ceramic materials and semiconductor, in the past twenty years. In this paper the development of the Accelerator and Electron ...     

一种低活化铁素体/马氏体钢的高能重离子辐照效应研究

低活化的铁素体/马氏体钢是先进核能装置（如聚变堆）的重要候选结构材料。 在聚变堆实际工作环境下, 由于高温和高氦产生率引起的材料失效是这类材料面临的一个重要问题。 本项研究以兰州重离子加速器（HIRFL）提供的中能惰性气体离子束（20Ne, 122 MeV）作为模拟辐照条件, 借助透射电子显微镜, 研究了一种低活化的9Cr铁素体/马氏体钢（T92B）组织结构的变化和辐照肿胀。 实验结果表明, 高温下当材料中晶格原子的撞出损伤和惰性气体原子沉积浓度超过一定限值时, 材料内部形成高浓度的空洞, 并且空洞肿胀率显著依赖于辐照温度和剂量; 在马氏体板条界面及其它晶界处空洞趋于优先形成, 并且在晶界交汇处呈加速生长。 基于氦泡的形核生长与空洞肿胀的经典模型探讨了在不同辐照条件（He离子、 Ne离子、 Fe/He离子双束、 快中子、 Ni离子）下铁素体/马氏体钢中肿胀率数据的关联。Low activation Ferritic/Martensitic steels are a kind of important structural materials candidate to the application in advanced nuclear energy systems. Possible degradation of properties and even failure in the condition of high temperature and high helium production due to energetic neutron irradiation in a fusion reactor is a major concern with the application of this kind of materials. In the present work microstructural evolution in a 9Cr Ferritic/Martensitic steel (T92B) irradiated with 122 MeV 20Ne ions at temperatures between 0.3—0.5 Tm (Tm is the melting point of the material) was investigated with transmission electron microscopy. High concentration voids were observed in the specimens irradiated at high temperatures when the displacement damage dose and Ne concentration exceed a certain level. Preferential formation of voids at lath boundaries and other grain boundaries was found. The data of void swellings in 9Cr ferritic/martensitic steels irradiated in different conditions (such as with He ions, Ne ions, Fe/He dual beams, fast neutrons, Ni ions etc.) were compiled and analyzed based on a classic model of helium bubble formation, and bubble to void transition.     

高压条件下高能重离子辐照材料研究进展

高能重离子辐照处于高压条件下材料的研究,是随着高能重离子加速器技术的快速发展而出现的一个新的研究领域, 研究结果涉及材料学、 地质学、地质年代学、核废料处理学等学科。简要介绍最近几年国内外在高能重离子辐照高压条件下材料研究领域的研究现状及已取得的结果,并对未来在兰州重离子加速器冷却储存环（HIRFL CSR）上开展相关研究工作的前景作了展望。With development of high energy heavy ion accelerator, it is possible to perform heavy ion irradiation experiments of pressurized materials in diamond anvil cells(DACs). It is a new research field. The results expected from irradiation experiments under high pressure will have impacts on several scientific fields such as materials science,geo science,geochronology,and nuclear waste storage. In this paper, some of recent works in this field are presented and reviewed. Furthermore,the research plan of materials under high pressure based on HIRFL-CSR is introduced.     

High temperature thermal behaviour modeling of large-scale fused silica optics for laser facility

High temperature annealing is often used for the stress control of optical materials.However,weight and viscosity at high temperature may destroy the surface morphology,especially for the large-scale,thin and heavy optics used for large laser facilities.It is necessary to understand the thermal behaviour and design proper support systems for large-scale optics at high temperature.In this work,three support systems for fused silica optics are designed and simulated with the finite element method.After the analysis of the thermal behaviours of different support systems,some advantages and disadvantages can be revealed.The results show that the support with the optical surface vertical is optimal because both pollution and deformation of optics could be well controlled during annealing at high temperature.Annealing process of the optics irradiated by CO2 laser is also simulated.It can be concluded that high temperature annealing can effectively reduce the residual stress.However,the effects of annealing on surface morphology of the optics are complex.Annealing creep is closely related to the residual stress and strain distribution.In the region with large residual stress,the creep is too large and probably increases the deformation gradient which may affect the laser beam propagation.     

Microstructure evolution of zircaloy-4 during Ne ion irradiation and annealing: An in situ TEM investigation

The microstructural evolution of zircaloy-4 was studied, including the amorphization and recrystallization of Zr（Fe, Cr）2 precipitates, and the density of dislocations under in situ Ne ion irradiation and post annealing. The results show that irradiation at a relatively high temperature and dose induces the formation of nanocrystals in pre-amorphized Zr（Fe, Cr）2 precipitates. The recrystallized nanocrystals also have the structure of hcp-Zr（Fe, Cr）2. The formation of the nanocrystals is thought to be the consequence of competition between atomistic disordering and the recrystallization of precipitates under ion irradiation. The free energy of the nanocrystal is lower than that of the amorphous state, which is another reason for the recrystallization of the precipitates. With increased annealing temperature, the density of the nanocrystals is increased. The dislocation density sharply decreases with the increase in the annealing temperature, and its size increases.     

先进核能系统结构材料辐照性能研究

首先简要介绍第一代到先进的第四代核能系统的发展、与核能系统发展密切的抗辐照结构材料研发进展、第四代核能系统结构材料辐照性能研究新方法。第四代核能系统发展中,辐照引起材料性能退化是一个需要研究和解决的瓶颈问题。现有中子源都不能满足第四代核能系统结构材料高剂量中子辐照性能研究的要求。为此,发展了用于核能系统结构材料高剂量辐照性能快速检测加速器重离子辐照方法和第四代核能系统实际辐照工况模拟的重离子与氢和氦三束同时辐照新方法,文中进行了详细的介绍。最后介绍了中国原子能科学研究院核能系统结构材料辐照性能研究现状和近期发展计划。该院在HI-13串列加速器器上建立了多种不同用途的重离子辐照装置、三个独立加速器构成的重离子与氢和氦三束同时辐照实验平台,开展了一系列核能结构材料,例如国产改进型奥氏体钢、CLAM钢、1515钢、钽、钨等的辐照性能的系统测试和研究。为了更好地开展核能结构材料性能研究,从国外引进了一台超导直线加速器和一台可变能量重离子回旋加速器。结合现有2×13 MeV,2×1.7 MV串列加速器、30 MeV和100 MeV质子回旋加速器、高压倍加器,中国实验快堆、中国先进研究堆、微堆等,CIAE将建成一个比较完整和先进的核能系统结构材料辐照实验平台系统供国内外用户使用。This paper introduces briefly the development of nuclear energy systems from the GEN I to the advanced GEN IV, the progress of manufacturing radiation resistant materials associated with the development of nuclear energy systems and the new methods of investigating radiation properties of the structural materials for the GEN IV nuclear energy systems at first. Irradiation induced deterioration of materials properties is a bottle neck problem, which must be investigated and solved for the development of the GEN IV nuclear energy systems. Unfortunately, all the currently available neutron sources cannot meet the requirements of investigating radiation properties of structural materials irradiated by high dose neutron irradiation in the GEN IV nuclear energy systems. Therefore, two new methods of the accelerator heavy ion irradiation that simulates the high-dose neutron irradiation and the triple beam irradiation that mimics the real neutron irradiation environment in the GEN IV nuclear energy systems have been developed. These two methods are introduced in this paper. The present status of the study on radiation properties of structural materials for nuclear energy systems of the new generation and the near future development plan at China Institute of Atomic Energy (CIAE) are described also. The accelerator heavy ion irradiation facilities for different applications and the simultaneous triple beam irradiation platform with three separate accelerators or implanters have been established at the HI-13 tandem accelerator of CIAE. A series of structural materials for nuclear energy systems, such as the home-made modified austenic steel, CLAM steel, 1515 steel, Tantalum, Tungsten, etc. have been tested and investigated systematically. A superconducting linear accelerator and a variable energy heavy ion cyclotron have been imported from abroad for a better performance of the study. Combined with the currently existing facilities of 2×13 MeV and 2×1.7 MV tandem accelerators, 30 and 100 MeV proton cyclotrons, China experimental fast reactor, China advance research reactor, Miniature neutron source reactor, etc. a comprehensive and advanced system of experimental irradiation platform for structural materials of nuclear energy systems will be established in the near future for both domestic and foreign users.     

抗辐照纳米多层膜研究进展

大量研究表明，晶界和界面可以作为吸收缺陷(如空位、间隙原子) 的“陷阱”，因此含有大量晶界、界面的纳米晶、金属和氮化物纳米多层膜，具备良好的自愈合抗辐照能力，从而成为近年来的研究热点。综述了抗辐照纳米多层膜的研究进展，内容包括:材料的设计与制备，各种辐照模拟手段(如中子辐照、离子辐照和多束离子辐照)。重点介绍了离子束辐照模拟反应堆辐照，多层膜在离子束辐照下的行为(如微观结构和机械性能的演变) 及纳米多层膜抗辐照机理。通过对CrN/AlTiN 多层膜的离子辐照，验证了纳米多层膜中界面对缺陷的吸收作用。对纳米多层膜未来研究方向做了展望。Numerous studies show that interface can serve as effective sinks for radiation-induced defects such as interstitials and vacancies. Owning a large number of interfaces, multilayer nanofilms attract a great research interest. In this paper, we review recent research progress on the development of the multilayer nanofilms for the purpose of radiation tolerance. The paper includes following parts: how to design and prepare multilayer nanofilms materials; evaluation with radiation simulation, such as neutron irradiation, ion irradiation and multi-beam ion irradiation; behaviors of multilayer nanofilms under ion beam irradiation, such as microstructure evolution and changes in mechanical properties; theoretical study on the mechanism of radiation tolerance of multilayer nanofilms. Finally, the challenge and future research directions are briefly discussed.     

利用高能离子模拟研究反应堆结构材料中的辐照效应

简要介绍了载能粒子辐射损伤对反应堆结构材料性能的影响,阐述了载能粒子束特别是高能离子束开展模拟研究的优势,并举例说明了国内利用高能重离子模拟研究反应堆结构材料辐射效应取得的进展。实验结果和理论分析表明,载能离子特别是高能离子辐照非常适合用于模拟研究反应堆结构材料中由粒子辐射引起的材料微观结构和宏观性能变化,是模拟研究反应堆结构材料辐射效应的非常有效的手段。 Radiation damage in structural materials of fission/fusion reactors is mainly attributed to the evolution of intensive atom displacement damage induced by energetic particles （ n, α and/or fission fragments） and highrate helium doping by direct α particle bombardments and/or （n, α） reactions. It can cause severe degradation of reactor structural materials such as surface blistering, bulk void swelling, deformation, fatigue, embrittlement, stress erosion corrosion and so on that will significantly affect the operation safety of reactors. However, up to now, behavior of structural materials at the end of their service can hardly be fully tested in a real reactor. In the present paper, damage process in reactor structural materials is briefly introduced, then the advantages of energetic ion implantation/irradiation especially high-energy heavy ion irradiation are discussed, and several typical examples on simulation of radiation effects in reactor candidate structural materials using high-energy heavy ion irradiations are introduced. Experimental results and theoretical analysis suggested that irradiation with energetic particles especially high-energy heavy ions is a very useful technique for simulating the evolution of microstructures and macro-properties of reactor structural materials.     

Effect of irradiation on microstructure and hardening of Cr–Fe–Ni–Mn high-entropy alloy and its strengthened version

ABSTRACT

A single-phase fcc high-entropy alloy (HEA) of 20%Cr–40%Fe–20%Mn–20%Ni composition and its strength with yttrium and zirconium oxides version was irradiated with 1.4?MeV Ar ions at room temperature and mid-range doses from 0.1 to 10 displacements per atom (dpa). Transmission electron microscopy (TEM), scanning transmission electron microscopy with energy dispersive X-ray spectrometry (STEM/EDS) and X-ray diffraction (XRD) were used to characterise the radiation defects and microstructural changes. Nanoindentation was used to measure the ion irradiation effect on hardening. In order to understand the irradiation effects in HEAs and to demonstrate their potential advantages, a comparison was performed with hardening behaviour of 316 austenitic stainless steel irradiated under an identical condition. It was shown that hardness increases with irradiation dose for all the materials studied, but this increase is lower in high-entropy alloys than in stainless steel.     

强流脉冲电子束作用下金属纯Cu的微观结构状态——空位簇缺陷及表面微孔结构

利用强流脉冲(HCPEB)电子束技术对多晶纯Cu进行了辐照处理,并利用透射电镜对HCPEB诱发的空位簇缺陷进行了表征.实验结果表明,HCPEP辐照金属可在纯Cu表层诱发大量的过饱和空位,并形成四方形空位胞及空位型位错圈和堆垛层错四面体(SFT),HCPEB瞬间的加热和冷却诱发的幅值极大的应力和极高的应变导致的整个原子平面的位移是空位簇缺陷形成的主要原因.此外,扫描电镜分析表明HCPEB辐照可以在纯Cu表面形成高密度、弥散分布和尺寸细小的微孔.过饱和空位或空位团簇沿晶体缺陷向表面扩散、凝聚是表面微孔形成的根     

Large scale silver nanowires network fabricated by MeV hydrogen(H~+) ion beam irradiation

A random two-dimensional large scale nano-network of silver nanowires(Ag-NWs) is fabricated by MeV hydrogen(H~+) ion beam irradiation. Ag-NWs are irradiated under H~+ion beam at different ion fluences at room temperature. The Ag-NW network is fabricated by H~+ion beam-induced welding of Ag-NWs at intersecting positions. H~+ion beam induced welding is confirmed by transmission electron microscopy(TEM) and scanning electron microscopy(SEM). Moreover, the structure of Ag NWs remains stable under H~+ion beam, and networks are optically transparent. Morphology also remains stable under H~+ion beam irradiation. No slicings or cuttings of Ag-NWs are observed under MeV H~+ion beam irradiation.The results exhibit that the formation of Ag-NW network proceeds through three steps: ion beam induced thermal spikes lead to the local heating of Ag-NWs, the formation of simple junctions on small scale, and the formation of a large scale network. This observation is useful for using Ag-NWs based devices in upper space where protons are abandoned in an energy range from MeV to GeV. This high-quality Ag-NW network can also be used as a transparent electrode for optoelectronics devices.     

Effect of implantation regimes of silver ions on the structure and optical properties of zinc-oxide nanocrystalline films

Thin (about 270 nm) nanocrystalline films of zinc oxide (ZnO) are obtained on quartz substrates using ion sputtering and irradiated with Ag⁺ ions at an energy of 30 keV and relatively high fluences at ion current densities of 4, 8, and 12 µA/cm². The X-ray analysis, scanning electron microscopy, and optical spectroscopy are used to study the effect of irradiation dose and ion current density on the structural modification and optical properties of the ZnO films. Nontrivial dependences of the structural and optical parameters of the films on the ion irradiation regimes are due to radiation heating and film sputtering under the action of the ion beam, diffusion of impurity, formation of silver nanoparticles in the irradiated layer at high implantation fluences, and the diffusion of implanted impurity at relatively high ion current densities.     

Structural modification in swift heavy ion irradiated muscovite mica

Two-layer monoclinic(2 M) muscovite mica sheets with a thickness of 12 μm are irradiated with Sn ions at room temperature with electronic energy loss( dE/dx)_e of 14.7 keV/nm. The ion fluence is varied between 1×10~(11) and1×10~(13) ions/cm~2. Structural transition in irradiated mica is investigated by x-ray diffraction(XRD). The main diffraction peaks shift to the high angles, and the inter-planar distance decreases due to swift heavy ion(SHI) irradiation. Dehydration takes place in mica during SHI irradiation and mica with one-layer monoclinic(1 M) structure is thought to be generated in 2 M mica after SHI irradiation. In addition, micro stress and damage cross section in irradiated mica are analyzed according to XRD data. High resolution transmission electron microscopy(HRTEM) is used on the irradiated mica to obtain the detailed information about the latent tracks and structural modifications directly. The latent track in mica presents an amorphous zone surrounded by strain contrast shell, which is associated with the residual stress in irradiated mica.     

激光辐照碲镉汞红外焦平面探测器的热应力损伤研究

基于碲镉汞红外焦平面探测器的结构与其材料热力学相关特征,描述了激光辐照碲镉汞红外焦平面探测器造成的损伤机理。根据相关的辐照环境和条件,通过有限元分析法建立了三维仿真模型。基于COMSOL Multiphysics软件仿真了碲镉汞红外探测器受到波长10.6 μm的激光辐照时,探测器各部分的温度变化及应力变化情况;通过数值分析方法,比较了碲镉汞探测器在经过光斑面积相同。功率不同的激光辐照后,其表面径向及内部轴向的温度场变化及应力场变化情况。仿真结果表明:在经过106 W/cm2的连续激光辐照后碲镉汞探测器表面温度与应力快速升高,造成探测器表面损伤,同时探测器被辐照部位的温度变化也导致其内部局部应力值变化。将碲镉汞探测器的应力损伤阈值及变化趋势与文献中相关实验数据进行对比,发现二者结果基本一致,验证了模型的可行性。     

碳化硅扫描反射镜支撑结构设计

对尺寸为460 mm×290 mm的SiC扫描反射镜的轻量化和支撑结构的设计进行了研究。基于三角形和矩形的复合轻量化结构,采用镜体背部为开放和封闭相结合的形式,设计了一种新型的扫描反射镜组件。该组件采用侧面支撑方式和轴向柔性结构,有利于消除支撑结构材料热膨胀系数不匹配产生的热应力对镜面面形的影响。有限元方法分析结果表明：反射镜组件在1 g重力载荷和8℃温度变化作用下,反射镜镜面的面形误差RMS值分别为4.5 nm和20.3 nm。该反射镜轻量化形式和支撑结构满足光学成像要求,并可有效提高结构的稳定性,对于大尺寸反射镜组件的设计具有借鉴意义。     

ASPIRE: An automated sample positioning and irradiation system for radiation biology experiments at Inter University Accelerator Centre,New Delhi

An automated irradiation setup for biology samples has been built at Inter University Accelerator Centre (IUAC), New Delhi, India. It can automatically load and unload 20 biology samples in a run of experiment. It takes about 20 min [2% of the cell doubling time] to irradiate all the 20 samples. Cell doubling time is the time taken by the cells (kept in the medium) to grow double in numbers. The cells in the samples keep growing during entire of the experiment. The fluence irradiated to the samples is measured with two silicon surface barrier detectors. Tests show that the uniformity of fluence and dose of heavy ions reaches to 2% at the sample area in diameter of 40 mm. The accuracy of mean fluence at the center of the target area is within 1%. The irradiation setup can be used to the studies of radiation therapy, radiation dosimetry and molecular biology at the heavy ion accelerator.     

Effect of vacuum arc ion beam treatment on the structure and mechanical properties of 30CrMnSiNi2A steel

The paper reports on a study of the structure and mechanical properties of 30CrMnSiNi2A high-strength steel irradiated with a Zr+ ion beam. The effect of irradiation on the steel was assessed by optical, transmission, and scanning electron microscopy as well as by X-ray di ITraction analysis of its irradiated and non-irradiated specimens 1 mm thick under static and cyclic tension, showing an increase in the fatigue life of the steel after irradiation. The deformation behavior and the mechanical properties of the specimens were compared, and the factors responsible for the increase in fatigue life were analyzed.     

铝靶激光热应力的实验研究

 用高温应变计和热偶计等诊断技术，研究连续波氧碘化学激光（CW/COIL）与铝合金板作用产生的激光热应力。当照射靶面激光强度约1 000 W/cm²时，激光热应力随靶厚的增加而快速减小。当激光辐照靶材厚度h＝1.00 mm、激光强度I＝640~980 W/cm²时，激光热应力随辐照靶面激光强度的增加而增大。两者的激光热应力－时间曲线随靶厚的减薄或随辐照靶面激光强度的增加而变得越来越复杂。当靶厚h≤2.50 mm，辐照靶面激光强度I≥800 W/cm²时，激光热应力强度超过激光辐照区材料断裂强度，萌生许多孔洞裂纹，引起材料断裂破坏。