PTFE表面辐照改性研究进展

聚四氟乙烯(PTFE)是一种具有润滑、绝缘及化学惰性的工程塑料,被广泛地用于电子、化工、纺织、医疗、机械、环境等领域。由于C—F键能高以及氟原子规整地排列在C—C链骨架上,因此PTFE表面能极低且表面润湿性和粘结性差,需要进行表面改性以增强PTFE与其它材料的界面亲和性。通过伽马射线/电子束和低温等离子体对PTFE进行辐照接枝改性和功能化修饰,能够有效地改善和优化其表面性能,使PTFE材料得到更好的利用。低温等离子体技术尤其适合PTFE表面改性处理,因为它不会导致PTFE本体材料的降解。本文综述了国内外关于PTFE表面辐照改性及应用的研究进展。     

环氧树脂对伽马射线的屏蔽分析及耐辐照效应

本文以环氧树脂为研究对象,分析了环氧树脂对能量范围在0.001~100 MeV的伽马射线的屏蔽性能,测试了环氧树脂对⁶⁰Co伽马射线的屏蔽性能,并对其进行了总剂量为93.5 kGy的伽马射线辐照处理,对辐照前后环氧树脂的密度、光学照片、力学性能、断面微观形貌、耐热性能和红外光谱进行了分析。结果表明：环氧树脂对低能(E<0.01 MeV)伽马射线的衰减主要是光电吸收作用,对中能(0.01 MeV60Co伽马射线的屏蔽性能一般。93.5 kGy伽马射线辐照导致环氧树脂老化、密度和最大耐热温度降低、力学性能增大、破坏程度低,环氧树脂可耐93.5 kGy伽马射线辐照。     

γ射线辐照合成石墨烯/银复合多孔气凝胶及其对硝基苯酚的催化性能

在乙醇/水体系及N_2氛围中,利用一步伽马射线辐照法将氧化石墨烯和银离子原位还原,并组装成具有三维网络结构的石墨烯/银复合多孔水凝胶(GH/Ag),通过冷冻干燥法得到石墨烯/银复合多孔气凝胶(GA/Ag)。通过场发射扫描电子显微镜观察到GA/Ag具有类蜂窝状的多孔网络结构;通过高分辨-透射电子显微镜可以观察到银纳米粒子尺寸范围在20～60 nm;并通过X射线光电子能谱、X射线衍射仪和热重分析等方法表明石墨烯/银纳米粒子复合材料中C元素含量增加,O元素含量降低,同时Ag+被还原及热稳定性增加。由于石墨烯和银纳米粒子之间的协同催化效应,GA/Ag对4-硝基苯酚表现出优异的催化性能,催化浓度高达2.16×10-3 mol/L。当4-硝基苯酚浓度为0.72×10~(-3)mol/L时,该催化反应一级动力学常数为1.53 min~(-1),远高于常规化学法制备的复合材料的催化性能。     

钴源与加速器辐照效应及辐照加工试验综合平台

辐照技术在核能、辐照灭菌和功能材料研发等应用领域具有独特的优势和不可替代的作用.本文主要介绍了中国科学院上海应用物理研究所钴源与加速器辐照效应及辐照加工试验平台.其中,0.5 MeV电子辐照试验装置可用于薄膜及纤维类等样品的连续辐照加工;1.5 MeV电子辐照试验装置主要用于小尺寸产品的间歇式辐照试验,并在第三代核电站...     

用射线处理木制家俱

【美国《新闻周刊》1980年6月9日报道】十几年来,新泽西州罗卡威的辐照技术公司一直在使用一种独特的伽马射线处理法生产供商业和住宅楼房中的地板用的坚硬、耐用的镶木和板条。这家公司现在又把它的辐照法用以生产耐磨而且容易保护的木料,这种木料可以用来做桌子及其他各种家具。这种辐照木料丙烯酸硬木加工法是把一块硬木放在一个压力室里浸以一种丙烯酸系塑性染料。当这块木料处于饱和状态时,用伽马射线对它进行照射,使木料孔隙中的染料凝固。这家公司声称,经这样处理,结果得     

氧化石墨烯对U(Ⅵ)的吸附

氧化石墨烯由于具有高比表面积和大量含氧功能基团，在放射性核素的高效富集方面引起广泛的关注。利用自制的氧化石墨烯作为吸附剂，研究了不同实验条件下对放射性废水中U(Ⅵ)的吸附行为，研究了pH、离子强度、温度和氧化石墨烯浓度对U(Ⅵ)吸附的影响。结果表明，氧化石墨烯对U(Ⅵ)的吸附主要是形成内层表面络合物，具有很强的去除能力，是目前所有材料中对U(Ⅵ)吸附能力最强的材料之一。吸附后的石墨烯经强酸处理后可以实现循环利用，而且吸附能力没有明显降低，但是弱酸处理不能使吸附的铀从石墨烯表面解吸。随着未来技术的发展，氧化石墨烯能够低成本大量制备后，在放射性废水处理中将具有重要的应用前景。     

中国抗中子辐照钢的抗辐照设计与验证

聚变堆等未来先进核能系统要求材料在强流高能中子辐照下长期保持良好的结构稳定性和机械性能。为适应未来先进核能技术发展的需要,中国科学院核能安全技术研究所•凤麟团队牵头研发了具有我国自主知识产权的中国抗中子辐照钢--CLAM钢。CLAM钢的设计考虑了未来核能清洁性的要求,以及苛刻服役环境中材料抗辐照、耐高温、耐腐蚀等性能要求。通过中子学计算分析设计了低活化成分范围,基于选择性纳米相析出进行了抗辐照、耐高温性能优化设计。针对材料的抗辐照性能,利用国内外中子、离子、电子及等离子体辐照设施开展了系列辐照考验研究,通过多角度表征辐照前后材料的微观结构和宏观性能,综合评估了材料的辐照性能,并与国际上同类材料在相近或相同条件下的辐照性能进行了对比分析,结果表明CLAM钢具有良好的抗辐照性能。     

关于国内首次采用遥控机械设备处置辐照卡源故障

介绍了国内利用核技术和自动化技术相结合,首次采用有线遥控机械设备处置辐照卡源故障.从辐照装置卡源后发生自燃及其爆炸的可能性,分析了对环境造成的影响.在高辐射场强下;利用遥控机械设备实现了信息、控制、机械、材料、核辐射与核技术等多学科技术联合攻关,取得了人机结合及机器人协调作业在工程中可靠应用等多项技术创新.     

伽马射线辐照制备还原氧化石墨烯

在氮气气氛中,以乙二胺(EDA)作为自由基捕获剂,利用γ射线辐照技术在水体系中将氧化石墨烯(GO)辐照还原功能化,制备高分散性的氨基功能化还原氧化石墨烯(rGO)。考察吸收剂量(5.3、15、20、35.3 kGy)对rGO还原程度和功能化程度的影响,并通过傅里叶变换红外光谱(FT-IR)、紫外-可见光吸收光谱(UV-vis)、X射线光电子能谱(XPS)、X射线衍射(XRD)和热重分析(TGA)等方法分析GO的化学结构及还原程度。直观上看,辐照后,GO溶液逐渐呈现棕黑色,随着吸收剂量的增加,溶液颜色加深,且具有良好分散性。FT-IR谱显示,经过γ射线辐照后,初始GO上的羰基被还原去除,EDA小分子被连接到了rGO片层上。UV-vis、XPS、TGA及XRD谱图表明,随着吸收剂量的增大可以使氧化石墨烯还原程度提高,当吸收剂量35.3 kGy时,C/O可达7.21。EDA有机小分子与氧化性的·OH反应,在无氧条件下转化为还原性的自由基,参与到与GO之间的氧化还原反应中,并被接枝到GO层的表面。     

中国抗中子辐照钢的抗辐照设计与验证

聚变堆等未来先进核能系统要求材料在强流高能中子辐照下长期保持良好的结构稳定性和机械性能。为适应未来先进核能技术发展的需要,中国科学院核能安全技术研究所·凤麟团队牵头研发了具有我国自主知识产权的中国抗中子辐照钢——CLAM钢。CLAM钢的设计考虑了未来核能清洁性的要求,以及苛刻服役环境中材料抗辐照、耐高温、耐腐蚀等性能要求。通过中子学计算分析设计了低活化成分范围,基于选择性纳米相析出进行了抗辐照、耐高温性能优化设计。针对材料的抗辐照性能,利用国内外中子、离子、电子及等离子体辐照设施开展了系列辐照考验研究,通过多角度表征辐照前后材料的微观结构和宏观性能,综合评估了材料的辐照性能,并与国际上同类材料在相近或相同条件下的辐照性能进行了对比分析,结果表明CLAM钢具有良好的抗辐照性能。     

InGaAsP多量子阱激光二极管及其组件的γ辐射效应

本工作进行多量子阱激光二极管及其组件的γ辐照实验研究,总剂量（以Si计）达5.5×10⁴Gy。结果表明：多量子阱激光二极管抗γ射线辐照能力很强,在实验总剂量下,裸管形式的多量子阱激光二极管的P-I特性、I-V特性及中心波长基本未变化。而多量子阱激光二极管组件因包含光学窗口、耦合透镜及光纤等附属光学元件,这些附属元件受γ辐照后光学性能下降,最终导致激光二极管组件输出光功率随总剂量增大而下降,停止辐照后,不需加偏置,在室温下即能发生退火,使得斜率效率逐渐回升。     

我国γ辐照装置辐射工作人员配置情况调查分析

我国γ辐照装置应用单位存在辐射工作岗位设置标准不统一、人员比例和配置数量不同、人员专业素质参差不齐、人员培训情况不同等问题。本文通过对国内较典型的11家动态、9家静态辐照装置单位共26座γ辐照装置的辐射工作岗位设置及人员配置情况进行调查与分析,提出对辐射工作岗位设置及最低人员配置的几点建议。     

CARR堆冷中子瞬发伽玛活化分析系统及实验研究

利用中国先进研究堆（CARR）在国内首次开展了冷中子瞬发伽玛活化分析（CNPGAA）实验,采用定制加长的电制冷高纯锗（HPGe）探测器和先进的数字多道谱仪DSPEC®-502进行测量,获得了NH₄Cl样品中元素冷中子瞬发伽玛谱和本底谱等数据,同时利用伽玛放射源¹⁵²Eu、¹³⁷Cs、⁶⁰Co以及NH₄Cl产生的瞬发伽玛射线对探测器在宽能区0.1~8 MeV进行能量刻度。为降低环境辐射本底,HPGe探测器外围采用环形锗酸铋（BGO）康普顿谱仪,10 cm铅以及含⁶Li和¹⁰B材料对中子束流准直屏蔽。此外,利用金片活化法测量了CARR堆运行功率为15 MW时有无冷源情况下冷中子导管B(CNGB)末端1 m处的中子注量率,结果显示有冷源时中子注量率可提高一个量级。     

Neutronics study for the installation of the LBVM in the medium flux area of IFMIF

IFMIF (International Fusion Materials Irradiation Facility) will be a fusion dedicated facility producing a large amount of neutrons with the appropriate energy spectrum to test materials and subcomponents for DEMO and future Fusion Power Plants.While the high flux area of IFMIF will be devoted to reduced activation structural materials for first wall and blanket, the medium flux area will be dedicated to functional materials for breeder blankets. In particular, the Liquid Breeder Validation Module (LBVM), will host experiments related with functional materials for liquid breeder blankets. Since IFMIF neutron spectra have been intended to fit the most irradiated areas of a fusion reactor in the high flux area, the irradiation conditions in the LBVM placed in the medium flux area of IFMIF have been assessed. The effect of some neutron shifter/reflector components to optimize the neutron spectra have been evaluated in order to find out the proper irradiation conditions for functional materials for liquid breeder blankets.Therefore, the objective of this report is to summarize the neutronic calculations developed to evaluate the viability of IFMIF neutron source to perform relevant irradiation experiments on functional materials for liquid breeder blanket concept for future nuclear fusion power reactors (ITER, DEMO). The irradiation parameters evaluated for this purpose are: the tritium production for liquid breeder material (Pb–17Li) and the damage dose (dpa) and gas production to damage dose ratios for Al₂O₃ and SiC functional materials.The main conclusion is that, it is possible to perform relevant irradiation experiments on functional materials for liquid breeder blanket concept for the future nuclear fusion reactor DEMO. Nevertless, the use of some shifter components will be needed to optimize some irradiation parameters.     

Effects of gamma-ray irradiation on crevice corrosion repassivation potential of stainless steel in high temperature diluted simulated seawater

The crevice corrosion repassivation potentials (E_R,CREV) of type 304 stainless steel (304 SS) were measured in high temperature (373–553 K), diluted simulated seawater under gamma-ray irradiation, in order to confirm the effects of gamma-ray irradiation on the crevice corrosion behavior of a representative stainless steel in seawater. Overall, for high temperatures, the E_R,CREV values decreased with increasing chloride ion concentration, which was the same as the behavior observed under the non-irradiated condition. The E_R,CREV values measured under gamma-ray irradiation were the same or slightly higher than E_R,CREV values measured under the non-irradiated condition when the [Cl^?] was the same. Consequently, it was confirmed that the threshold potential of crevice corrosion of 304 SS for the gamma-ray irradiation of 1.8 kGy at least did not deteriorate compared with the non-irradiated condition. Under the conditions of this work (seawater composition, [Cl^?] range, dose rate, absorbed dose, flow rate, etc.), the crevice corrosion of 304 SS could be suppressed by maintaining the potential below the threshold potential which was determined approximately as ?0.3 V vs. SHE even for the irradiated condition at temperatures up to 553 K.     

Effects of gamma-ray irradiation on electronic and non-electronic equipment of Large Helical Device

In a deuterium operation on the Large Helical Device,the measurement and control equipment placed in the torus hall must survive under an environment of radiation.To study the effects of gamma-ray irradiation on the equipment,an irradiation experiment is performed at the Cobalt-60 irradiation facility of Nagoya University.Transient and permanent effects on a personal computer,media converters,programmable logic controllers,isolation amplifiers,a web camera,optical flow meters,and water sealing gaskets are experimentally surveyed.Transient noise appears on the web camera.Offset of the signal increases with an increase of the integrated dose on the programmable logic controller.The DeviceNet module on the programmable logic controller is broken at the integrated dose of 72 Gy,which is the expected range of the integrated dose of the torus hall.The other equipment can survive under the gamma-ray field in the torus hall.     

Characterization of dose delivery in a hard X-ray irradiation facility

The Radiation Bioengineering Laboratory at Seoul National University (SNU) operates a user-constructed hard X-ray irradiation facility for radiation biology and radiation therapy physics studies. The system package of YXLON model 450-D08 operating at the anode voltage of up to 450 kV is a key part of the facility, which enables in vitro cell irradiation and animal irradiation for in vivo studies. In this article, dose delivery in the hard X-ray irradiation facility was characterized in terms of the dose vs. operational parametric combination of the facility. The operational parameters included beam tube anode voltage, beam tube current, irradiation time, and beam exit-to-sample distance. Bremsstrahlung X-rays at energy below approximately 20 keV were filtered out by a 3 mm-thick aluminum plate fitted over the 5 mm-thick beryllium window. Gafchromic EBT films were used as radiation sensor materials in dose measurement. The characterization was validated via experimental observation of the in vitro biological responses of cells to radiation exposure. The biological responses obtained using the new hard X-ray irradiator were highly comparable with those obtained using a commercial gamma-ray irradiator.     

Experimental simulations of planetary gamma-ray spectroscopy using thick targets irradiated by protons

To simulate planetary gamma-ray spectroscopy, gamma rays were measured during a series of five irradiations of up to 30-ton thick targets with protons beams of 1.5 and 2.5 GeV. The targets were steel (iron), basalt with structural steel, basalt with added S and Cl, and basalt with added H, S, and Cl. The pulsed proton beam was carefully monitored and counted. Spectra were collected with both proton beam on and beam off and with a lead shield both between the target and the germanium detector and with the lead shield removed. This set of four spectra was used to determine the fluxes of prompt gamma rays emitted from the target. Over 200 discrete gamma-ray lines per irradiation were observed and identified. Counting results for the more intense gamma rays were compiled, and gamma-ray fluxes determined for about 25 gamma rays of interest to planetary gamma-ray spectroscopy. The ratios of thermal and fast neutron induced gamma-ray fluxes between irradiations were similar. Thus the relative gamma-ray fluxes can be used in testing model calculations and interpreting planetary gamma-ray spectra.     

Effect of gamma-ray irradiation on the deoxygenation of salt-containing water using hydrazine

In spent fuel pools at the Fukushima Daiichi nuclear power plant, hydrazine was added to salt-containing water in order to reduce dissolved oxygen. Hydrazine is known to reduce dissolved oxygen in high-temperature pure water, but its deoxygenation behavior in salt-containing water at ambient temperature in the presence of radiation is unknown. Deoxygenation using hydrazine in salt-containing water was thus investigated using a ⁶⁰Co gamma-ray source and artificial seawater at room temperature. Water samples containing a small amount of hydrazine were irradiated at dose rates of 100–10,000 Gy/h. The concentration of dissolved oxygen in the water samples was measured before and after irradiation. Notably, a decrease in the dissolved oxygen was only observed after irradiation, and the dissolved oxygen concentration decreased with increasing dose rate and irradiation time. The rate of decrease in the amount of dissolved oxygen using hydrazine was slow in the presence of salts. Kinetic considerations suggested that the deoxygenation of the salt-containing water exposed to gamma-ray irradiation using hydrazine was suppressed by chloride ions.     

Effects of Heat-Treatment and Gamma-Ray Irradiation on the Etch-Pit Formation in Allyl Diglycol Carbonate Resin

Allyl diglycol carbonate resin plates possessing alpha tracks were etched after heat-treatment, or after gamma-ray irradiation. The strong heat-treatment and irradiation brought similar effects to two indicators: etch-pit diameter and bulk etching rate. The heat-treatment above 120°C lasting for 1h and irradiation above 4.0x10² Gy increased the indicators and caused the etch-pits to disappear faster. On the other hand, mild heat-treatment brought the opposite effects to under-cured resin. A reduction of the etch-pit diameter was observed in the resin exposed to heat-treatments between 80°C and 120°C lasting for 1h. These phenomena were observed in the study of plates in which alpha tracks were made after the above mentioned heat-treatment or irradiation. These results suggest not only the conditions under which the resin may be used, but also the possibility of enhancement or suppression of etching speed, and of estimation of thermal history or measurement of gamma-ray dosage.