纳米碳中的微观缺陷结构特征

测定了定向石墨和纳米碳的正电子寿命谱,结果表明,热解法制备的纳米碳存在开空间小于单空位的自由体积以及开宽间相当于约１０个空位聚集体全的微孔洞,比较了热解法制备的纳米碳,ＵＦＰ冷压法制备的纳米Ｆｅ和纳米ＴｉＯ２以有非晶晶化法制备的纳米ＮｉＰ的缺陷结构特征,结果为纳米ＮｉＰ中缺陷的电子密度最高,纳米Ｆｅ和纲米ＴｉＯ２次之,纳米碳的最低,纳米碳中的缺陷浓度最高,纳米Ｆｅ和纳米ＴｉＯ２的次之,纳米ＮｉＰ的     

金属中空位及空位团的正电子寿命谱

本文从理论上讨论了金属中正电子湮没寿命和金属的空位、空位团的体积的关系,利用密度泛函和交换关联能的局域密度近似,系统地计算了一系列金属中不同空位团的正电子寿命值。可以看出,正电子湮没技术是研究金属微观缺陷结构的有力手段。     

用正电子湮没寿命技术研究塑性变形纯Ni的回复过程

本文用正电子湮没寿命方法研究了塑性变形镍(含0.01％杂质)的回复过程的特点及杂质在缺陷回复过程的作用和影响,计算了形变为10％的试样中的位错密度及形成空位团的有效空位浓度。     

正电子湮灭技术对镍和不锈钢辐照效应的初步探讨

用正电子湮灭技术研究金属中的缺陷,最近十多年来有着迅速的发展。正电子湮灭寿命、湮灭光子的角关联和多普勒加宽这三种实验方法对于晶体的缺陷都很灵敏。尤其对于空位、位错、空位聚集体等空位型缺陷特别灵敏。因此,这些方法在金属材料的辐照损伤研究中引起了人们特有的兴趣。本文用正电子湮灭技术研究了72.5MeV的碳离子(_(12)C~( 4))轰击镍和不锈钢的辐照效应,测量了它们的正电子湮灭寿命和多普勒加宽线形参数S。另外,还用高压透射电子显微镜和位错热激活法进行了测量。并对经过辐照和未经过辐照样品的测量结果进行了对比。这三种实验方法给出了一致的定性结果。     

用正电子湮没研究12Cr1MoV钢蠕变损伤

采用正电子寿命测量研究了12Cr1MoV钢的蠕变损伤。寿命谱按三分量自由拟合进行分析。正电子平均寿命τ、缺陷寿命τ_2及其强度I_2随着蠕变损伤率的增加而增加。与形变和疲劳的研究结果不同,正电子寿命参数并未出现饱和现象。此外,当蠕变损伤率D>1％时,τ_2和τ_3增加很快,I_3可达到10％。这些特征有力地说明了在蠕变过程中空位导致空位团的生成,最后形成微孔洞。     

新型U3Si2-Al燃料板的正电子湮没寿命谱研究

用正电子湮没寿命谱仪对U3Si2-Al燃料板样品的正电子湮没寿命进行了测量及分析,得到不同工艺状况下燃料包壳材料微观缺陷的形态及变化趋势.回火态燃料板包壳基体中的微观缺陷以单空位的点缺陷为主;冷作态中的缺陷以双空位、位错等缺陷为主;冲刷态中的缺陷以层错、小的空位团等缺陷为主.3种样品中,均未发现影响燃料板安全的大空位团缺陷.回火和冲刷等工艺或运行工况,会使燃料板包壳基体中的微观缺陷发生转变,并改变了燃料板的宏观力学性能.     

热塑弹性体SEBS中溶剂影响的正电子谱学研究

利用正电子湮没寿命谱方法观察了因三嵌段共聚物(SEBS)浇铸成膜时所使用的溶剂不同给SEBS膜中自由体积的大小和浓度带来的影响,从而看到了由于微相分离结构的存在而对自由体积变化产生的影响。     

质子辐照钼退火行为的正电子寿命谱学研究

室温下用3.2MeV质子对多晶纯钼样品进行了辐照,用正电子寿命测量技术研究了辐照损伤及晶格缺陷在293～1138K温区内的退火行为,得出了许多有关空位团生长以及氢-缺陷相互作用的信息。辐照后在Mo中产生2～3个空位的聚集体,其浓度随辐照剂量增加而增加。从所测得正电子寿命、强度参数的变化获知高温退火后空位团的增长行为以及氢原对空位团长大的影响。     

质子辐照钼退火行为的正电子寿命谱学研究

室温下用3.2MeV质子对多晶纯钼样品进行了辐照,用正电子寿命测量技术研究了辐照损伤及晶格缺陷在293～1138K温区内的退火行为,得出了许多有关空位团生长以及氢-缺陷相互作用的信息。辐照后在Mo中产生2～3个空位的聚集体,其浓度随辐照剂量增加而增加。从所测得正电子寿命、强度参数的变化获知高温退火后空位团的增长行为以及氢原对空位团长大的影响。     

中子辐照硅的正电子湮没研究

采用正电子湮没方法研究了１．４５×１０＾２０ｎ／ｃｍ＾２和３．１０×１０＾１７ｎ／ｃｍ＾２快中子辐照高纯单晶硅的辐射损伤及其退火效应。在３４３－１０７３Ｋ温度范围内测量了正电子湮没寿命随退火温度的变化。实验观察到氧－空位对和在高中子剂量辐照的Ｓｉ中发现的双空位复合成四空位。正电子湮没短寿命成分τ１是晶格正电子寿命和氧－空位对捕获的正电子寿命的加权平均值，而长寿命成分τ２是双空位或四空位捕获的正电子     

Identification of radiation treatment of wheat （Triticum aestivum. L）and rice （Oryza sativa. L） samples using thermoluminescence of contaminating minerals

Food irradiation is gaining popularity worldwide and this technology is important to improve quality and reduce the post harvest losses of food. Because of the rapid commercialization of irradiated foods throughout the world, compliance of different regulations relating to use of technology in different countries and demand of consumers for clear labelling of irradiated foods, there is need for the development of analytical methods to detect radiation treatment of food. Among several methods studied so far, thermoluminescence （TL） is an important method that can be used to find out the irradiation history of food that contain even a very minute amount of dust particles. In this study, the irradiated and unirradiated wheat and rice samples were analyzed using the TL method. The samples were purchased from the local market of Peshawar and irradiated to radiation doses of 0.5 and 1.0 kGy using Co-60 gamma irradiator at the Nuclear Institute for Food and Agriculture （NIFA）, Peshawar. The mineral contaminants were isolated by jet water, ultrasonic treatment, and density gradient. TL glow curves of the isolated minerals from irradiated and unirradiated samples were recorded between the temperature ranges of 50-500℃ using a TL reader. Generally, the glow curves for irradiated samples showed much higher TL intensities （TL1） than the unirradiated samples. The results were normalized by rerradiation of mineral samples to gamma-ray dose of 1.0 kGy followed by determination of the second glow curves （TL2）. The ratio of the area of first glow curve to that of second glow curve （TL1/TL2） was calculated for selected temperature intervals and compared with the recommended values for unirradiated and irradiated samples. Finally, the shapes of the glow curves for irradiated and unirradiated samples were also analyzed. On the basis of these results （comparison of TL-intensities, TL1/TL2 ratios and shapes of the glow curves）, all the irradiated and unirradiated samples of wheat and rice were unequivocally identified.     

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.     

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。     

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.     

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.     

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.     

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.     

The preclinical pharmacological study of dopamine transporter imaging agent 18F-FP-β-CIT

The paper is to study pharmacologic characteristics of 18F-FP-β-CIT (18F-N-(3-fluoropropyl)-2β- carbomethoxy-3β- (4-iodophenyl)nortropane) as an imaging agent for dopamine transporter. The radiochemical purity of 18F-FP-β-CIT in aqueous solution was over 95% after standing at room temperature for 4h. Biodistribution displayed rapid uptake in rat brain (1.375 %ID/organ at 5min and 0.100 %ID/organ at 180 min) and the striatal uptake was 1.444,0.731, 0.397, 0.230 and 0.146 %ID/g at 5, 30, 60, 120 and 180 min, respectively. The values of striatum/cerebellum,striatum/frontal cortex and striatum / hippocampus in rat's brain at 30 min were 3.38, 2.17 and 2.40 respectively. The uptake in striatum can be blocked by β-CFT, suggesting that 18F-FP-β-CIT binds to DAT peculiarly. The compound was rapidly cleared from monkey's blood. The striatal uptake was bilaterally decreased in the left-sided lesioned PD rats, compared with normal control. Brain PET imaging studies in normal monkey showed that 18F-FP-β-CIT was concentrated in striatum. The test of undue toxicity showed that the dose received by mice was 1250 times as by human, which indicates that 18F-FP-β-CIT is very safe. So 18F-FP-β-CIT is a promising PET imaging agent for DAT with safety and validity.     

The role of AGFA high-energy CR in the calibration and quality control of multileaf collimators （MLC）

Linear accelerators equipped with multileaf collimators （MLC） are becoming more common and are widely used in the intensity-modulated radiotherapy （IMRT）. There is an imperative need to ensure the commissioning specification of the linear accelerators for the sake of quality assurance （QA） and quality control （QC）. This paper is aimed to investigate the role of AGFA high-energy CR （Computed Radiography） in calibrating dynamic multileaf collimators and evaluating the accuracy of the leaf position. The result shows that AGFA high-energy CR can easily and conveniently be used to calibrate MLC and verify its position. Hence, the application of AGFA high-energy CR is proved to be an accurate and time-saving method for routine MLC QC, especially when MLC calibration adjustments are required.