光聚合一步可控合成表面氨化的核壳型超顺磁性纳米凝胶及其表征

用部分还原共沉淀结合离心分离合成超顺磁性Fe3O4纳米粒子,以其为核,N-（2-氨乙基）甲基丙烯酰胺盐酸盐N-（2-Aminoethyl）methacrylamide,AEM·HCI）为单体,N,N＇-亚甲基双丙烯酰胺（MSA）为交联剂,采用光聚合原位一步合成粒径可控的表面氨化的超顺磁性核壳型Fe3O4纳米凝胶。探索了单体、交联剂量及光照时间对纳米凝胶粒径的影响,并用动态光散射仪（DLS）、TEM、FTIR、TGA、UV、多功能磁测量仪等表征了纳米凝胶的粒径、粒径分布、形貌、结构、磁响应性及稳定性。结果表明：改变单体、交联剂量及光照时间可得到不同粒径、粒径分布均匀的超顺磁性纳米凝胶;与Fe3O4纳米粒子相比,纳米凝胶的磁饱和强度略有降低,但其高的Zeta电位使其稳定性大大提高。     

纳米聚N-异丙基丙烯酰胺微凝胶的光引发聚合

选择具有温敏性的高分子单体N－异丙基丙烯酰胺（N－isopropylacrylamide，NIPAM）为主单体，N，N′－亚甲基双丙烯酰胺（methylenebisacrylamide，MBA）为交联剂，运用光引发无皂乳液聚合的方法合成出粒径小于100nm的高分子微凝胶，并研究了在改变体系组成和条件时微凝胶粒径的变化。结果显示，在乳化剂临界胶束浓度以下，随着乳化剂浓度的提高，微凝胶粒子的粒径不断关小且趋向稳定；相比于热引发，产生的微凝胶具有较高的单分散性而且粒径较小。     

反相微乳液体系中电子束辐射制备Fe3O4/聚丙烯酰胺磁性核壳微球

在共沉淀法制备Fe3O4纳米磁粉的基础上,以丙烯酰胺(Acrylamide,AM)为单体在反相微乳液中通过电子束辐照的方法制备了具有核壳结构的四氧化三铁/聚丙烯酰胺磁性核壳微球(Fe3O4/Polyacrylamide,PAM),用X射线衍射仪、原子力显微镜、傅立叶变换红外光谱、动态激光光散射仪表征样品.结果表明,制备的磁粉为Fe3O4单相,粒径为9nm左右,磁性高分子微球Fe3O4/PAM直径范围为80-150 nm,呈球形.分析了乳化剂用量,单体浓度,磁粉用量,吸收剂量等对Fe3O4/PAM微球粒径的影响规律.     

聚丙烯酰胺包覆磁性纳米凝胶的光化学法制备及其机理研究

以丙烯酰胺为单体，N，N’-亚甲基双丙烯酰胺为交联剂，采用光化学方法在水溶液体系中制备了聚丙烯酰胺（Polyacrylamide，PAM）包覆的磁性纳米凝胶，用傅立叶变换红外光谱（Fourier transform infrared spectroscopy,FTIR），光子相关光谱（Photo correlation spectroscopy,PCS）和电子自旋共振（Electron spin resonance，ESR）波谱对聚丙烯酰胺磁性纳米凝胶进行了表征。研究了磁性纳米凝胶粒径随反应时间、单体浓度、交联剂浓度的变化规律，并探索了聚丙烯酰胺磁性纳米凝胶的包覆机理。     

葡聚糖修饰Fe_3O_4磁性纳米粒子的同步辐射光电子能谱研究

在纳米Fe3O4表面修饰葡聚糖可在粒子表面建立空间位阻稳定层,不仅提高了纳米粒子在水中的分散稳定性,还增强了纳米粒子的生物相容性.本文在柠檬酸钠介质中合成了葡聚糖修饰的Fe3O4纳米粒子,采用同步辐射X射线光电子能谱(XPS)对未经修饰和葡聚糖修饰后的Fe3O4纳米粒子表面的化学组分、表面原子的化学结构、化学键合情况进行了定性和定量分析,并给出葡聚糖修饰Fe3O4纳米粒子的反应机理.结果表明,反应体系中的柠檬酸钠首先在Fe-O-C键包覆到Fe3O4纳米粒子表面,然后葡聚糖分子与纳米粒子外的COO-以氢键结合并同时发生葡聚糖大分子缠绕包裹连接到纳米粒子表面,这大大增强了反应体系的分散稳定性和葡聚糖修饰氧化铁纳米粒子的亲水性.     

Fe_3O_4/聚丙烯酸/CdS复合粒子的光化学制备及光催化性能

采用光引发丙烯酸聚合的方法对Fe3O4纳米粒子进行表面改性,制备了羧基功能化的Fe3O4/聚丙烯酸复合纳米粒子(Fe3O4/PAA);以Fe3O4/PAA为磁核,以硫酸镉和硫代硫酸钠为原料,采用光化学方法制备Fe3O4/聚丙烯酸/CdS复合粒子(Fe3O4/PAA/CdS),并借助红外光谱、X射线粉末衍射、透射电子显微镜、荧光光谱和振动样品磁强计对其进行表征。结果表明,核-壳结构的Fe3O4/PAA/CdS为表面粗糙的球形粒子,平均粒径为155 nm,具有发光性能和准超顺磁性。Fe3O4/PAA/CdS在有机染料罗丹明B的降解实验中显示出良好的可见光催化活性,可以借助磁铁在2 min内从溶液中完全回收。     

快速响应PNIPA／Fe3O4复合凝胶辐射制备与性能研究

采用化学共沉淀法制备了四氧化三铁粒子,以N-异丙基丙烯酰胺（NIPA）、N,N-亚甲基双丙烯酰胺（MBA）和聚乙二醇（PEG）为原料,以60Coγ,射线为放射源,辐照聚合制备了多孔PNIPA／Fe3O4复合水凝胶,并对其温度敏感性、平衡溶胀率进行了表征。研究发现：磁性四氧化三铁纳米粒子在凝胶中分散均匀;凝胶具有明显的温度敏感性;致孔剂的添加提高了水凝胶的平衡溶胀率,多孔复合水凝胶失水率达96％,比普通磁性水凝胶失水率提高了约76％;致孔剂的添加使复合凝胶的最低临界相转变温度由34℃升高至37℃左右。     

Au/Fe3O4磁性复合粒子的光化学制备

用紫外光辐照含有纳米 Fe3O4磁流体的氯金酸和聚乙烯醇的水溶液,制备了 Au/Fe3O4磁性复合粒子,并用紫外.可见光谱、X射线衍射和透射电镜对其进行了表征.磁性复合粒子中Au纳米粒子具有面心立方结构,其等离子共振吸收峰分布较窄,说明金纳米粒子的粒径分布较均匀.TEM表明该复合粒子具有团簇状结构,由许多Au和Fe3O纳米粒子构成,尺寸介于70-230 nm范围.对照实验表明聚乙烯醇是Au纳米粒子与Fe304之间复合的必需媒介,据此提出了生成团簇状Au/Fe3O4磁性复合粒子的可能机制.     

电子束辐照制备的纳米硫化镉研究

在常温常压下，采用电子束辐照法在水溶液体系中合成了纳米硫化镉粒子。X射线衍射分析表明该产物为面心立方结构晶体的纳米硫化镉；透射电子显微镜分析表明该纳米粒子形貌呈球状颗粒，平均粒径为15nm；其光学性能研究表明，其紫外吸收光谱的吸收边波长为487nm；激发波长为350nm时，纳米粒子的荧光发射波长的峰值为476nm，主要为由带边发射引起的发光。用激光粒度仪研究了表面活性剂聚乙烯醇浓度对辐射制备纳米硫化镉粒径的影响，在一定范围内随着聚乙烯醇浓度的增大，纳米粒子的粒径相应减小。     

磁性纳米微粒的制备方法及其在放射免疫分析中的初步应用

采用化学共沉淀法合成水溶性正癸酸包覆的Fe3O4磁性纳米微粒,并以此为核心物理吸附羊抗兔IgG制备磁性纳米第二抗体,作为磁性分离载体用于放射免疫分析中。用光子相关光谱仪与透射电镜测定了磁性纳米微粒的粒径大小、粒径分布和多分散度等。研究了羊抗兔IgG包被磁性纳米微粒的包被介质的pH、羊抗兔IgG用量和包被时间等制备条件对磁性纳米微粒二抗免疫反应结合能力和非特异结合的影响。结果表明：化学共沉淀法制得的Fe3O4平均粒径约为10-20nm,吸附羊抗兔IgG后其平均粒径为1000nm左右,并可用于放射免疫分析中。提示羊抗兔IgG可通过物理吸附的方法固定在磁性纳米微粒上,其优点是制备方法简便、省时和成本低,在放射免疫分析中具有磁性分离的方便性,具有较大的医学应用价值。     

Preparation of Zn/TiO2 powder and its photocatalytic performance for oxidation of P-nitrophenol

Zn-doped TiO2 catalysts were prepared using a sol-gel method and characterized by XPS,UV-Vis, BET, XRD in this study. Under the irradiation of simulant sunlight, the photocatalytic activity for the degradation of p-nitrophenol was studied too. After irradiation for 2.5 h, the degradation percentage of p-nitrophenol could rise to more than 80 %. The results showed that the spectrum absorption band edge of Zn/TiO2 powder does not broaden obviously comparing with pure TiO2 powder. Zinc exists as Zn （11）. When calcined at 973 K, there is a new phase as ZnTiO3 in Zn/TiO2 catalyst. The order of photocatalytic activity of Zn/TiO2 catalysts calcined at different temperatures for p-nitrophenol is 773 K 〉 673 K 〉 873 K 〉 573 K 〉 973 K and the photocatalytic activity of Zn/TiO2 catalyst calcined at 773 K is better than TiO2 catalysts heated at the same temperature, and outclasses that of commercial TiO2 catalyst. It also showed that the photocatalytic degradation of p-nitrophenol follows first-order kinetics under the irradiation of simulant sunlight.     

Current status of radiation therapy for prostate cancer

Radiotherapy for the treatment of prostate cancer has been extensively explored in the past. Along with the comprehensive understanding of the biology of prostate cancer and rapid advances in terms of technology, the out- come of treatment for the patients with prostate cancer has improved. The authors review radiotherapy as the primary treatment for the disease, with particular emphasis on the technological advances from both the radiobiological and radiophysics aspects. Nonconventional fractionated irradiation like hyper- or hypo-fractionation has been imple- mented in the clinic, the final results still need to be confirmed in the future. Technological advances like IMRT, IGRT, in the last two decades have significantly improved the delivery of external radiotherapy to the prostate. This has re- sulted in an overall increase in the total dose that can be safely delivered to the prostate, which has led to modest im- provements in the biochemical outcome. However, establishing the standard therapy for prostate cancer remains con- troversial. It is hoped that the next decades will bring continued advances in the development of biologicals that will further improve current clinical outcomes.     

The control system for SSRF injection and extraction

This paper introduces the injection and extraction control system design for SSRF,which is a distributed control system aimed at stability and reliability of the pulse power supplies,PPS(Personnel Protection System)and MPS(Machine Protection System).The hardware environment is mainly based on PLC(Programmable Logic Con- troller),and ARM(Advanced RISC Machine)is also applied for studying stability of the power supplies.WinCC and EPICS(Experimental Physics and Industrial Control System)have been selected as the platforms of SCADA(Super- visory Control and Data Acquisition).For unifying the interfacing to the control computer,all front-end equipments are connected via Industrial Ethemet.     

水平管内含空气蒸汽强制对流冷凝换热模型研究

为研究含空气蒸汽在水平管内强制对流冷凝换热特性,基于对传热传质过程的分析,建立了管内为环状流与波状流条件下的流动冷凝换热模型。从潜热、显热和液膜3个环节对整个换热过程进行建模,最终得到计算局部冷凝换热系数的理论关系式。模型预测结果与实验数据的对比表明,二者相对偏差在±20%以内,验证了该换热模型的准确性与适用性。通过进一步的研究发现：从换热管入口至出口,随着冷凝的进行,管内换热主要热阻由液膜热阻向气液界面的凝结热阻转变;主流气体对流换热过程基本可忽略。     

Investigations on landmine detection by BF3 detector

Experiments were carried out to investigate the possible use of neutron backscattering for the detection of polyethylene (PE) sample buried in the soil. In detection of landmine by neutrons, the neutron detector and its shield play an important role. In this paper, the effects of graphite, heavy water, polyethylene and boric acid moderators on the flux of back scattered neutrons were investigated. We have also experimentally verified the effect of BF3 detector shield and obtained good agreement with theory.     

Web Services interface of SSRF archive data analysis system

Accelerator database stores various static parameters and real-time data of accelerator. SSRF (Shanghai Synchrotron Radiation Facility) adopts relational database to save the data. We developed a data retrieval system based on XML Web Services for accessing the archive data. It includes a bottom layer interface and an interface applicable for accelerator physics. Client samples exemplifying how to consume the interface are given. The users can browse, retrieve and plot data by the client samples. Also, we give a method to test its stability. The test result and performance are described.     

有效探测面积大于1000 cm2的正比计数器测量系统性能测试

为对自制的活性面积高达1 000 cm²的大面积源进行表面发射率定值,同时作为现有2πα、2πβ表面发射率标准装置能力的扩充,研制了一套内置式大面积2π多丝正比计数器测量系统,并利用活性区直径为8 mm的²⁴¹Am点源及活性区面积为10 cm×15 cm的大面积²⁴¹Am和⁹⁰Sr-⁹⁰Y源对其进行计量学性能测试。结果表明：计数器内计数响应均匀性优于±0.4%,有效探测面积达1 400 cm²;所得²⁴¹Am源高压坪曲线的坪长为1 400 V,坪斜为0.27%/100 V,坪区内计数变化为0.87%;⁹⁰Sr-⁹⁰Y源高压坪曲线的坪长为300 V,坪斜为0.75%/100 V,坪区内计数变化为0.80%;10次测量重复性好于0.4%,8 h内短期稳定性好于0.3%,1 a内长期稳定性好于0.8%。     

Assessment of radioactivity levels in some oil samples from the western desert, Egypt

Distributions of natural gamma-emitting radionuclides were determined in 93 oil samples collected from some petroleum fields in the western desert of Egypt. The radioisotope activities in the area under investigation lay in the range of (21 ± 4) to (38 ± 13) Bq?L-1 for 226Ra, (9 ± 2) to (15 ± 5) Bq?L-1 for 232Th, and (154 ± 28) to (303 ± 54) Bq?L-1 for 40K. The mean values were 27, 12, and 201 Bq?L-1, respectively. Among oils, variations in radionuclide ac- tivities could be on account of differences in TDS, HCO3, and Ba, with high or low pH. In this environment, oil prop- erties differently affected the mobilization of natural radionuclides. The range of 226Ra variation had been compared with available data from other countries. The calculated absorbed dose rate ranged from 22.33 to 32.66 nGy?h-1 in lo- cation (B) and (E) respectively, which was less than the accepted value.     

Preparation and properties of 117m Sn(IV)-TTHMP in in-vitro and in small animals

In this work,TTHMP was synthesized and labelled with 117m Sn.The preparation conditions,stability and lipophilicity of 117m Sn(IV)-TTHMP were investigated.Biodistribution of the complex in rabbits and mice was studied.It was found that the quantity of TTHMP and pH value of the prepararion solution had vital effects on the labeling yield of 117m Sn(IV)-TTHMP.It was also found that 117m Sn(IV)-TTHMP was hydrophilic and stable at room temperature and 37℃ in open air 117m Sn(IV)-TTHMP showed unexpectedly high bone uptake and bone-to-blood ratio in the animals.This made it potentially useful as an reagent for skeletal scintigraphy and radiotherapy of bone tumors.     

Gamma radiation levels in the ambient environment of the QNPP Base

Monitoring results of gamma dose rate level in 1992～2004 in the ambient environment of the Qinshan Nuclear Power Plants(QNPP)Base,the northeast of Zhejiang Province,are reported in this paper.It is shown that the gamma dose rate of five monitoring sites of 2.5 km to QNPP Base is 84～113 nGy/h,with an average of 96 nGy/h in the 13 years.The average value is close to the background level of 93 nGy/h prior to operation of the QNPP Base,and is lower than the monitoring result of 101 nGy/h at the reference site in Hangzhou City.Within 50 km from the QNPP Base,the cumulative dose rate of the thermoluminescent dosimeter(TLD)is 90 nGy/h,which is lower than the back- ground level of 111 nGy/h.