THGEM探测器化学抛光及其工作气体优化

采用新的化学抛光方法处理THGEM膜,在不同的气体成分和比例下对THGEM膜的增益和能量分辨进行研究测量。结果表明,以Ar/C_4H_(10)为工作气体的THGEM探测器所需工作电压较低、增益高、能量分辨相对较好。在Ar/C_4H_(10)(95%/5%)的气体条件下,THGEM的增益可达7×10~3。     

薄型较大面积THGEM气体探测器的研制

为满足环形正负电子对撞机项目配置的需要,研制了薄型较大面积THGEM气体探测器。该探测器工作时不需要额外的腔室,并且其厚度能达到8 mm,较原来的11 mm有明显减少。其有效面积为20 cm×20 cm,其增益在Ar/iC_4H_(10)(97/3)工作气体中能达到10~4倍,最好能量分辨为30%,增益均匀性能达到88.5%,探测器增益也呈现出较好的长期稳定性。     

栅型气体电子倍增器的研制

实践中发现,微结构气体探测器(MPGD)遇到三方面挑战:打火时放电电流的抑制与稳定运行、单元面积增大后的生产工艺以及孔型结构带来的探测位置重建偏差。为解决以上问题,本文提出了一种新型结构的MPGD——栅型气体电子倍增器(Groove)。使用3种不同几何尺寸的栅型电极,在不同气体中对8.04 keV铜靶X射线的能谱进行测量,以检验探测器性能。与蒙特卡罗模拟计算结果对比表明,探测器信号主要来自雪崩产生的离子。能谱测量结果显示:栅极狭缝宽度0.2 mm、厚度0.8 mm的探测器增益和能量分辨率好于其他尺寸的探测器;在93%Ar+7%CO_2中运行时,探测器增益与分辨率两项指标稍好于在95%Ar+5%CH_4中。测量得到的探测器增益最高可达3×10~4左右,能量分辨率最高可达15.6%。     

栅型气体电子倍增器的研制

实践中发现，微结构气体探测器（MPGD）遇到三方面挑战：打火时放电电流的抑制与稳定运行、单元面积增大后的生产工艺以及孔型结构带来的探测位置重建偏差。为解决以上问题，本文提出了一种新型结构的MPGD--栅型气体电子倍增器（Groove）。使用3种不同几何尺寸的栅型电极，在不同气体中对8.04 keV铜靶X射线的能谱进行测量，以检验探测器性能。与蒙特卡罗模拟计算结果对比表明，探测器信号主要来自雪崩产生的离子。能谱测量结果显示：栅极狭缝宽度0.2 mm、厚度0.8 mm的探测器增益和能量分辨率好于其他尺寸的探测器；在93%Ar+7%CO₂中运行时，探测器增益与分辨率两项指标稍好于在95%Ar+5%CH₄中。测量得到的探测器增益最高可达3×10⁴左右，能量分辨率最高可达15.6%。     

固体反冲质子辐射转换体THGEM快中子探测器特性模拟研究

使用Geant4模拟研究了基于聚乙烯辐射转换材料的THGEM快中子探测器的辐射转换特性。结果表明,探测器响应具有一定阈特性,其灵敏度、响应阈值随辐射体厚度、吸收层厚度、中子入射角度、辐射体面积变化而改变。中子垂直入射,聚乙烯辐射体厚度50μm、铝吸收层厚度10μm时,探测器阈上响应具有较好的坪特性,阈值为2.2 MeV,灵敏度为1.0×10-4cm2。     

一种多极平行板雪崩探测器

描述了一种为RIBLL研制的在线束流监测用双维位置灵敏多极平行板雪崩探测器(Multi-platePPAC)。它主要由中心阳极、两个位置灵敏栅极和两个阴极平面组成。灵敏面积为100mm×100mm。使用异丁烷工作气体,气压稳定在650Pa,阳极在+400V,阴极在-350V时,对三组分α源测得探测器的位置分辨约0.58mm(FWHM),位置非线性±50μm,探测效率好于99.2%。由于该探测器明显的高增益,它适合探测较高能量的较轻粒子。     

中重离子焦面探测器系统的研制

研制了一套中重离子焦面探测器系统(500mm长),已通过束流检验并用于核物理实验中。该探测器望远镜是由5个矩形正比管组成,采用30％CH_4 70％Ar为工作气体。桌上试验:位置灵敏探测器的本征分辨约0.7mm(FWHM),积分非线性好于0.2％;回旋加速器试验:ΔE探测器分辨约6.3％,E探测器的能量分辨约为10％;在串列加速器上,以60MeV,~(12)C束流,在0.5×10~5Pa压力下,测得位置的本征分辨约1.3mm,最大积分非线性好于0.62％,ΔE探测器的能量分辨约6％;E探测器的能量分辨约31％。     

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%。     

中重离子焦面探测器系统的研制

研制了一套中重离子焦面探测器系统(500mm长),已通过束流检验并用于核物理实验中。该探测器望远镜是由5个矩形正比管组成,采用30％CH_4 70％Ar为工作气体。桌上试验:位置灵敏探测器的本征分辨约0.7mm(FWHM),积分非线性好于0.2％;回旋加速器试验:ΔE探测器分辨约6.3％,E探测器的能量分辨约为10％;在串列加速器上,以60MeV,~(12)C束流,在0.5×10~Pa。压力下,测得位置的本征分辨约1.3mm,最大积分非线性好于0.62％,ΔE探测器的能量分辨约6％;E探测器的能量分辨约31％。     

厚GEM探测器对γ射线探测效率的研究

作为一种新型微结构气体探测器(MPGD),厚型气体电子倍增器(THGEM)用于较高能量光子探测是新的尝试。为了解其探测机理及探测效率的主要影响因素,利用多粒子输运软件、多物理耦合仿真软件及气体电离模拟软件,分别建立了光子与探测器相互作用模型、电子漂移扩散模型和气体电离模型。通过仿真得到了漂移极内表面和膜上电极的电子出射概率,~(137)Cs在漂移极内表面产生激发电子的能量分布和角分布。动态模拟了电子在特定电场中的漂移和横向扩散行为,定量计算了原初电子的入孔数量和入孔效率。最后通过实验验证,证明增大漂移区距离和提高THGEM膜间电压可显著提高THGEM对γ射线的探测效率。     

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.