高能136Xe离子辐照聚酰亚胺化学改性的电子能损效应

用1．755GeV^136Xe离子在真空室温环境下辐照叠层聚酰亚胺薄膜,通过红外和紫外光谱测量研究了高电子能损离子辐照引起的化学降解及炔基产生效应。红外测量结果表明,典型官能团随辐照注量的增加指数降解,且径迹芯中所有官能团均遭到破坏;对应8．8(最小能损,第一层)和11．5keV／nm(最大能损,第五层)电子能损,^136Xe辐照聚酰亚胺的平均降解半径分别为3．6和4．1nm。而相应能损条件下炔基的生成截面分别为5．6和5．9nm大于官能团的降解截面。紫外结果表明辐照引起的吸光度的改变随辐照注量线性增加,发色团的产生效率随电子能损的增大而增加。     

1.23 GeV Fe离子在C60薄膜中形成潜径迹的Raman谱分析

用能量为1.23GeV的快Fe离子辐照了多层堆叠的C60薄膜。用Raman散射技术分析了快Fe离子在C60薄膜中由强电子激发引起的效应，主要包括辐照引起C60分子的聚合及其高温、高压相（HTHP）的形成，和在高电子能损下C60晶体点阵位置上的C60分子向非晶碳的转变。由此演绎出了快Fe离子在C60薄膜中的损伤截面或潜径迹截面σ和潜径迹的半径心，及其随沉积在电子系统中的能量密度的变化而变化的规律。     

高能重离子辐照制备SiOC复合材料的研究

用120 kev碳离子注入非晶SiO2薄膜,再用高能Xe、Pb和U离子辐照.注碳剂量范围为2.0×1017-8.6×1017 cm-2,高能离子辐照剂量1.0×1010-3.8×1012 cm-2.辐照后的样品用傅里叶变换红外光谱仪进行系统分析.实验结果显示,高能离子辐照在注碳非晶SiO2薄膜中形成了大量的Si-O-C键和Si-C键.这些Si-O-C结构具有环链、开链和笼链等多种结构形式.随电子能损、辐照剂量或者沉积能量密度的增加,SiOC结构由类笼向环/开链结构演化.对高能重离子驱动产生SiOC结构的机理进行了简单的讨论.     

C60薄膜在快重离子辐照下的结构稳定性研究

用傅立叶变换红外光谱、X射线衍射谱、X射线光电子谱和拉曼散射技术分析了能量为GeV量级的S、Fe、Xe、和U离子,以及120keV的H离子在室温下辐照多层堆积C60薄膜的结构稳定性,即快重离子在C60薄膜中由高密度电子激发引起的效应,主要包括C60分子的聚合、分子结构的损伤、新的高温-高压相的形成和晶态向非晶态的转变.     

高能氩离子在钇铁柘榴石中引起的非晶化研究(英文)

用倾斜样品X-射线衍射学(STD)和饱和磁化强度测量,研究了960MeV氩离子低温(195K)辐照多晶钇铁柘榴石Y_3Fe_5O_(12)(YIG)所引起的非晶化过程。分析结果表明,960MeV氩离子引起YIG晶态→非晶态转变是一个逐步的过程,在这个过程中电子能损起主导作用,但也需要一定的辐照剂量。并在辐照剂量0≥1×10~(14)Ar/cm~2时,在电子能损S_e=8.3MeV处,首次观察到了几乎完全的非晶态。     

200 keV Xe离子辐照后国产T92钢微结构变化研究

对国产T92钢进行200keV的Xe离子辐照试验,使用透射电子显微镜(TEM)考察该能量下不同辐照损伤剂量对其微观结构的影响,研究结果表明:T92钢典型的微观组织结构主要包括马氏体板条结构,碳、氮化合物颗粒和位错网络;辐照导致M23C6颗粒出现非晶化,且随着辐照损伤剂量的增加,非晶化越来越明显;辐照损伤剂量较小(1.4dpa和6.8dpa)时,辐照试样中出现黑斑结构(空位和间隙原子簇),所有的辐照试样中没有发现辐照产生的位错环和空洞。     

不同能量和注量电子辐照对InP HEMT材料电学特性影响

本文采用气态源分子束外延法(GSMBE)制备了匹配型InGaAs/InAlAs磷化铟基高电子迁移率器件(InP HEMT)外延结构材料。针对该外延结构材料开展了不同能量和注量电子束辐照试验,测试了InP HEMT外延结构材料二维电子气（2DEG）辐照前后的电学特性,获得了辐照前后InP HEMT外延材料二维电子气浓度和迁移率归一化退化规律,分析了不同能量和注量电子束辐照对外延材料电学特性的影响。结果发现：在相同辐照注量2×1015 cm-2条件下,电子束辐照能量越高,InP HEMT外延材料电学特性退化越严重;15 MeV电子束辐照时,当辐照注量超过4×1014 cm-2后,外延材料电学特性开始明显退化,当电子辐照注量达到3×1015 cm-2后,外延材料电学特性退化趋势减弱趋于饱和。产生上述现象原因如下：电子束与材料晶格发生能量传递,产生非电离能损(NIEL),破坏晶格完整性,高能量电子束具有较高的非电离能损,会产生更多的位移损伤缺陷,导致InP HEMT外延材料电学特性更严重退化;InP HEMT外延材料电学特性主要受沟道InGaAs/InAlAs异质界面能带结构和各种散射过程影响,随着电子辐照注量的增加,位移损伤剂量增大,辐射损伤诱导缺陷会在沟道异质界面处集聚直至饱和。     

高能铁离子辐照单晶氧化铝产生的色心研究

室温下利用紫外-可见吸收光谱和荧光光谱技术对1.157GeV的56Fe离子注入辐照的单晶三氧化二铝(α-Al2O3)进行了测量分析,研究了辐照产生的阴离子空位的形成和演化规律.测量结果显示,高能Fe离子辐照产生了多种阴离子空位型缺陷,其中包括F、F 、F2 、F22 和F2心.随入射离子剂量的增加,各类缺陷的数量逐渐增大,并在高剂量时趋于饱和,但各类缺陷间的相对数量存在一定的比例,不随剂量的增加而有明显变化.用单离子饱和损伤模型对实验结果进行了拟合,获得各类色心的产生截面在40-90 nm2之间.与TRIM程序计算结果比较后发现,室温下辐照时阴离子单空位的产生速率约是由核能损过程在低温下产生缺陷速率的一半.     

高能氩离子在钇铁柘榴石中引起的非晶化研究

用倾斜样品X-射线衍射学(STD)和饱和磁化强度测量,研究了960MeV氩离子低温(195K)辐照多晶钇铁柘榴石Y_3Fe_5O_(12)(YIG)所引起的非晶化过程。分析结果表明,960MeV氩离子引起YIG晶态→非晶态转变是一个逐步的过程,在这个过程中电子能损起主     

高能铁离子辐照二氧化硅玻璃产生的缺陷研究

室温下用紫外-可见吸收光谱、荧光光谱和电子顺磁共振技术测量分析1.157 GeV56Fe离子辐照的二氧化硅玻璃,研究了高能重离子辐照产生缺陷的规律.紫外-可见吸收光谱测量结果显示,高能铁离子辐照产生了包括E'心、非桥连氧空穴心(NBOHC)和缺氧心ODC(Ⅱ)在内的多种缺陷结构.随着离子辐照量的增加,各类缺陷的数量逐渐增大并在高辐照量时趋于饱和.用单离子饱和损伤模型对实验结果进行拟合,获得了各类缺陷的产生截面在90-140 nm2.根据缺陷相对数量的变化关系探讨了E心和NBOHC的产生机制.荧光光谱显示,当以5 eV的紫外光激发辐照样品时,观测到三个荧光发射峰,分别位于4.28 eV(α带)、3.2 eV(β带)和2.67 eV(γ带),α带和γ带的存在证实辐照产生了ODC(Ⅱ)缺陷.实验发现β带是二氧化硅玻璃中的一种固有缺陷,高能离子辐照可使其部分脱色.电子顺磁共振测量进一步证实了E'心的产生规律.     

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.     

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.     

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.     

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.