碳剥离膜结构的研究

碳剥离膜可用交流电弧法或直流电弧法来制备,也可用交直流电弧来做多层膜.不同制备方法的碳剥离膜有不同的寿命,表明不同制备方法的碳膜有着不同的微观结构.本文对不同制备方法的碳剥离膜的微观结构做了SEM/TEM照片测试,分析了碳剥离膜结构对碳剥离膜寿命的影响.     

碳剥离膜的制备

采用辉光放电裂解然法和碳弧法,为串列为加速器制备了长寿命碳剥离膜,研究了裂解室的阳极尺寸和阳,阴极之间的距离对裂解碳膜均匀性的影响,用分光光度法测量了碳剥离膜的厚度。     

乙烯裂解法制碳膜

近十年来,在测定碳剥离膜的寿命上,各国做了一些工作,确认了碳剥离膜的寿命t是正比于E/(M_1Z_1~2φ)此处E是入射粒子的能量;M_1、Z_1分别是入射粒子的原子量和原子序数,φ是入射粒子流密度。有几个实验室证明了碳剥离膜的寿命亦是依赖于制膜的特殊技术的,根据他们的测量结果指出,用Ar~( )束来轰击,在相同的轰击的物理参数下,乙烯裂解的碳膜,比电弧的碳膜寿命可长到30倍。为了能得到这种乙烯裂解的碳膜,最近我们建立了一套这种方法的做膜装置,并成功地做成了面密度均匀的、厚度可在几微克/cm~2～几十微克/cm~2之间、面积可达65×55mm~2的这种碳膜。我们曾以能量为42keV的N~ 束和C~ 束(我所分离器引出束)来轰击电弧蒸发的碳膜和乙烯裂解的碳膜,束流直径是4mm,束流强度是0.3μA,由于我们的入射粒子质量太轻,轰击时间又被限止,当这二种膜各经受了二个多小时的轰击后,没有看到膜破就被取下。因此,我们还期待国内外可提供有稍完善的低能重离子的加速器的条件下,再进一步做轰击寿命实验。但我们初步在某些物理性能上比较了这二种碳膜,所得的显著的差异的结果与以上所提的参考文献中的结论是一致的。     

类金刚石碳剥离膜的制备及其性能研究

采用磁过滤阴极真空弧(FCVA)技术制备了质量厚度为5~7μg/cm2的类金刚石碳(DLC)剥离膜。用XP2U型精密电子天平测试分析了100mm范围内的DLC剥离膜均匀性,结果显示其最大不均匀性小于10%。通过扫描电子显微镜(SEM)、原子力显微镜(AFM)、万能摩擦磨损试验机和X光电子谱(XPS)测试分析了DLC剥离膜的表面形貌、耐磨损特性和结构,结果显示采用双90°FCVA技术沉积的DLC剥离膜表面光滑致密、耐磨,几乎没有大颗粒的污染,表征金刚石特性的sp3键含量超过70%。在北京HI-13串列加速器上使用107 Ag-、70 Ge-、48 Ti-、28Si-、197 Au-和127I-六种典型质量的离子束对质量厚度为5~7μg/cm2的DLC剥离膜和碳剥离膜寿命进行测试比较,结果显示DLC剥离膜寿命比碳剥离膜的高2.6~10倍。     

用CsI作分离剂制备自支承碳膜

本文介绍一种用CsI作分离剂制备自支承薄碳膜的方法。由碳膜制成的碳靶在核物理实验中是一种常用的靶,在对碳的核物理测量实验中更是不可缺少的。由于碳的原子序数比较低,所以在做其他物质的核反应实验中,常用它来做靶的底衬。我们曾用肥皂液作分     

U形靶框-双层结构碳剥离膜制备

本研究涉及用于兰州重离子加速器冷却储存环上的碳剥离膜的制备方法。该剥离膜采用特殊的U形靶框和双层结构，使膜的强度大为加强，以提高高真空条件下剥离膜使用寿命。采用碳弧法制备的剥离膜的有效面积较大，为10cm²，质量厚度约为150μg/cm²。碳剥离膜的X衍射谱测试结果表明，膜上的碳以非晶体石墨形式存在。     

碳剥离膜的厚度对电荷态分布的影响

在SSC加速器的前束流输运线上探索碳剥离膜的厚度对被剥离后束流电荷态分布的影响,是本实验的目的。因为作为SSC的注入器,我们回旋加速器束流的引出能量较高,因此碳剥离膜的平衡厚度要求大大超过一般用在串列静电加速器头部所使用的碳膜厚度,有人曾用公式x(μg/cm~2)=5.9285+22.386w-1.1292w~2来估计碳膜的平衡厚度与能量之间的关系,误差范围为100％。式中,w以MeV/A为单位。为了研究碳剥离膜的厚度对束流电荷分布的影响我们进行了如下实验。     

碳弧法制备碳膜

文章介绍了碳弧装置的结构和碳弧放电法制备碳膜的工艺过程。该法能获得自支撑Ｃ膜的最小和最大厚度分别为４和２０００μｇ／ｃｍ＾２。Ｃ膜的厚度用分光光度法和称重法测量．     

碳剥离膜在HIRFL-CSR的应用和电荷态分布的测量

兰州重离子加速器冷却储存环主环的离子注入方式包括剥离注入和多圈多次注入。在剥离注入中,带电离子通过碳膜后的电荷态分布对注入效率有较大影响。本工作对离子通过碳膜后的电荷态分布进行了测量,并阐述了兰州重离子加速器冷却储存环上剥离器的应用,给出了离子通过碳膜后电荷态分布的测量结果。     

医用重离子加速器U型碳剥离膜的研制

碳剥离膜作为剥离器的核心组成部件是医用重离子加速器的重要装置之一,研制出满足医用重离子加速器要求的碳剥离膜至关重要。采用交流弧光放电法完成了医用重离子加速器中碳剥离膜的研制,并用扫描电子显微镜和拉曼表征手段测试分析了碳剥离膜的薄膜特性。为了不影响已注入环中离子的正常运行,靶框设计为U型,靶边框较窄仅为2 mm,碳剥离膜的有效面积为1 600 mm~2(40 mm×40 mm)。碳剥离膜的厚度为15μg·cm~(-2),理论计算结果表明该碳剥离膜的厚度均匀性为97.65%。碳剥离膜具有一定的机械韧性,可以完成碳剥离膜的自动换膜过程,且在自动换膜过程中无破裂损伤。扫描电子显微镜观测结果显示:碳剥离膜的表面平整,内部结构致密。拉曼测试结果表明:位于1 580 cm~(-1)附近的G峰明显强于位于1 300 cm~(-1)附近的D峰,说明薄膜的石墨化程度较高;2 700 cm~(-1)左右的2D峰较弱,说明石墨分子层数较多。     

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.