气体电子倍增器(GEM)探测器

气体电子倍增器(GEM)作为一种新型气体电离室探测器,具有结构简单、性能卓越、兼容性强等优点,广泛应用于高能物理、核物理等多个领域。介绍了GEM探测器的原理、研究现状及发展应用。     

气体电子倍增器的研制及性能测试

气体电子倍增器(GEM)以其独特的性能在辐射探测器领域得到了广泛的应用,对50μm厚聚酰亚胺(kapton)薄膜利用真空热蒸发和激光掩膜打孔法制作GEM膜,孔径100μm,孔距223μm,并封装流气式探测器,有效探测面积3mm×3mm。5.9keV55F e X射线测量了GEM在不同高压和混合气体比例时的脉冲幅度分布情况。讨论了高压和气体比例对探测器计数率和能量分辨率的影响。结果表明GEM具有较高的信噪比,能量分辨率可达18.2%。     

带增益的气体探测器读出ASIC的研制

设计了用于带增益的气体探测器比如GEM、RPC等读出的ASIC,实现对探测器信号的放大、成形和对后续实时采样ADC的驱动电路.电荷增益和成形时间可调,有利于探测器不同增益下性能的研究,也扩展了芯片的应用范围.由于成形电路引入的噪声变得显著,在低电荷增益下,ENC会随增益下降而增加.芯片采用Chartered 0.35μm2P4M CMOS工艺,论文介绍了芯片的详细设计和仿真结果.     

大面积GEM膜制作方法研究

正近年来气体电子倍增器(GEM)成为新一代微结构气体探测器的主要发展方向,在国际上得到迅速发展。作为整个GEM探测器的核心的大面积GEM膜研制,在我国微结构探测器研究领域有着重要需求。目前我国参加的重大国际合作CERN LHC上ALICE实验和JLab 12GeV升级SoLID谱仪的建设都将用到GEM探测器。通过与CERN合作,掌握了制作大面积GEM膜的关键技术,确定研制大面积GEM膜需解决的关键问题,包括如何实现GEM膜制作过程中从掩膜板到GEM原膜精确的图像转移和如何实现大面积GEM膜的均匀性。并由此确定GEM膜制作的     

基于粒子-蒙特卡洛模型的气体电子倍增探测器的研究

采用粒子一蒙特卡罗模型(Particle in Cell-Monte Carlo Collision,PIC-MCC)对气体电子倍增探测器(Gaselectron multiplier,GEM)的倍增放大过程进行了模拟,这对更好的理解和把握GEM的物理机理具有重要的意义.在电场分析的基础上,从GEM空间粒子数和粒子的空...     

一种新的气体电子倍增模式的研究

介绍了一种新的气体放大器件--GEM,制作了一个有效面积为100mm×100mm的GEM+MWPC的模型.用5.9 keV的X射线源测量它的气体倍增系数,并研究了不同气体比例(Ar/CO2)下GEM的放大的性能.GEM的放大倍数可达到94倍.     

蓬勃发展的位置灵敏气体探测器

介绍了近年来气体位置灵敏探测器的发展,简要描述了几种新型的高位置分辨、高计数率的探测器：MSGC、MGC、MICROMEGAS、GEM等。     

基于APV25读出电子学系统的GEM探测器的位置分辨与X射线成像研究

采用3层GEM膜制作了有效面积为10 cm×10 cm的GEM探测器,该探测器采用二维条读出方式,条间距为400 μm,每个维度有256个读出通道。探测器的读出采用APV25读出电子学系统,根据GEM探测器的需要,设计并改进了电子学系统使用的背板连接器。实验测得GEM探测器空间分辨为76 μm。进行了X射线二维成像研究,获得了清晰的二维图像,探测器与电子学运行稳定可靠。     

基于GEM探测器的数字读出芯片研制

研制了一种适用于高能物理GEM探测器读出系统的数字芯片。芯片采用PAD读出方式,对GEM探测器的输出直接采样,对采样到的信号放大并成形,判断该输入是否超过由外部DAC设定的阈值,给出判断结果,并按照一个串行协议读出。芯片采用0.35μm/3.3 V CMOS工艺设计,后仿真结果显示芯片达到预期研制目标。     

一种新型气体探测器的研制

加速器质谱(accelerator mass spectrometry,AMS)技术因探测对象不同,探测器也应根据需要进行选择。为建立低能量重离子加速器质谱测量技术,本文设计制作一台新型气体探测器并调试应用。该探测器采用厚度50 nm,膜面积8 mm×8 mm的氮化硅膜作为入射窗。采用5.48 MeV的241Am源的α粒子对探测器进行调试,调试后将该探测器安装于中国原子能科学研究院的300 kV小型AMS系统上进行129I粒子测量。经模拟计算以及对探测器的调试、应用,证明该探测器具有较高的能量分辨率,可以很好的实现不同粒子的鉴别,同时测量灵敏度可达到10^-13国际水平,满足低能量重离子的测量要求。     

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.     

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。     

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.     

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.