一种高速宽带放大与峰值保持电路的研制

主要介绍了一种高速宽带放大与峰值保持电路.该电路是根据束流位置监测系统的要求而研制的,是该系统的前端部分.主要包括放大电路和峰值保持电路两部分,其主要特点是采用直流耦合的方式对微弱快电压信号进行多级放大,使得信号在放大过程中不会产生附加相移,此外还采取差分放大的方式来有效地抑制直流耦合带来的直流漂移.电路带宽≥70MHz,增益≥700.     

分立元件的RF宽带放大电路研制

介绍一种由新研制的由分立元件组成的快放大器。该电路是一个交流耦合放大器,具有较高的电源增益（Av≥500）,快的上升延（tr≤1．7m）,低噪声（等效到输入端噪声vn≤3μs）,该放大器主要用于我所束流诊断系统中放大来自相位探针的微弱信号。     

一种抑制高增益直流耦合放大电路中直流漂移的电路

直流漂移现象在直流耦合放大电路中是不可避免的,放大器的放大倍数愈大,在输出端出现的直流漂移现象就愈严重.本文提出了一种可以有效抑制高增益低噪声直流耦合快前置放大电路中的直流漂移的电路.将此电路用于我们所设计的高增益(Av≥1000)直流放大器中,有效抑制了输出端的直流漂移.对该放大器进行了100h的工作测试,结果输出直流漂移小于±3mV.     

共面栅碲锌镉探测器读出电路设计及性能研究

为有效读出共面栅碲锌镉(CPG-CZT)探测器的核脉冲信号,本文结合CPG-CZT探测器工作原理及国内外研究,设计了可用于CPG-CZT探测器的读出电路,主要包括高压偏置电路、前置放大电路、增益调节及减法电路。为研究读出电路性能,本文测试了各单元电路的性能及探测系统能量分辨率随偏置电压、增益调节电路中两路信号的相对增益G的变化规律。结果表明：高压偏置电路两路输出偏压与输入偏置电压的相关系数R²均为0.998;前置放大电路输出噪声为5 mV;增益调节及减法电路输出信号噪声为10 mV;输入偏置电压、相对增益G的变化均会影响探测系统能量分辨率,当偏置电压为-1650 V、相对增益G为0.7时对¹³⁷Cs源产生的γ射线能量分辨率最佳,可达3.65%,且无明显拖尾现象。     

基于CdZnTe探测器的核素探针探头的研制

为了解决在核医学手术中使用放射性核素进行病灶定位的难题,设计了一种基于碲锌镉(CdZnTe)探测器的核素探针探头。该核素探针探头主要包含CdZnTe探测器、低噪声电荷灵敏前置放大器和快驱动电路。考虑到环境本底和外界电磁干扰,对探针探头的结构作了特殊设计,该特殊设计能够提高核素探针探头的探测能力。探头中的放大器和快驱动电路能明显的放大核脉冲信号的幅度和提高核脉冲信号的信噪比,便于后端信号处理分析系统对信号的进一步处理。     

束流均匀性测量前端读出电子学电路的设计

针对重离子治癌中的束流监测需要,用T型反馈电阻网络组成的电流-电压转换(IVC)电路将大面积二维位置灵敏平行板雪崩探测器( PPAC)输出的多路10pA～100 nA的微弱电流转换成-2V～-20 mV的电压信号,配合数据获取处理系统实现了近代物理研究所重离子治癌中的束流均匀性测量.实验表明该电路具有速度快、精度高等优...     

半导体探测器输出电流检测系统前置放大器设计

为满足半导体探测器输出电流检测系统的需求,设计了与之相适应的前置放大器。该前置放大器基于超低偏置电流运放ADA4530,采用单个反馈电阻和T型反馈网络的I/V变换前置放大电路组成。测试结果表明:该前置放大器的放大倍数可达10 mV/pA,直流偏移为8μV;对于pA级分辨率,其输出噪声电压频谱密度仅为17.75 nV/(Hz)~(1/2),输出总噪声为409μV;可用于μA~pA范围内的核辐射探测器电流信号测量。     

基于阻容低通反馈的电荷灵敏前置放大器的设计

传统电荷灵敏前置放大器以高阻值电阻作为低频反馈端,高阻值电阻所引入的热噪声为前置放大器噪声的主要来源。本文以N沟道结型场效应晶体管和阻容(Resistor-Capacitance,RC)电路构成低通网络代替传统高阻值反馈电阻完成了新型电荷灵敏前置放大器的研制。该电路以结型场效应晶体管和集成运算放大器构成放大电路,具有高输入阻抗及大开环增益的优点;以小容值电容构成高通回路,为电路提供高频反馈回路,同时实现核脉冲电流的积分;以RC低通网络构成直流反馈回路,为电路提供一个稳定的直流工作点,同时构成电压分压器使N沟道结型场效应管工作在正向偏置状态,实现对反馈电容中的电荷进行连续放电。相比于传统阻容反馈式电荷灵敏放大器,该电路能够有效克服大阻值反馈电阻引入的噪声,尤其适用于Si-PIN等半导体探测器。将该电荷灵敏前置放大器与BPX66型Si-PIN探测器连接,在室温下对241Am源进行测量,其能量分辨率可达到3.03%@59.5 keV。     

分布电容对微电流放大器响应性能影响分析及实验研究

本文分析比较了基本放大电路、T型反馈放大电路、高频补偿T型反馈放大电路和并联补偿放大电路四种微电流放大电路的响应特性。研究了转移电阻和布线引入的分布电容对放大电路增益和响应速度的影响。探讨了影响微电流放大器的稳定性、可靠性因素以及提升放大器的稳定性和可靠性的措施。对并联补偿放大电路脉冲响应的时间常数进行了测试,测试结果为80μs。理论分析和实验研究表明,并联补偿放大电路具有增益大、响应速度快等优点,稳定性好,可靠性高,在离子迁移谱中具有良好的应用前景。     

基于碳化硅探测器的前端信号调理电路设计

碳化硅探测器能够在高温、高辐射强度下稳定工作,适用于核辐射探测。碳化硅探测器输出端连接前端信号调理电路,能够放大碳化硅探测器输出的微弱信号,从而使后端设备采集到准确的数据。设计了前端信号调理电路,包括电荷灵敏前置放大电路和脉冲成形主放大电路,重点分析了影响电荷灵敏前置放大电路变换增益、上升时间、噪声等性能指标的影响因素,采用阻容反馈、极零相消、有源滤波成形等设计提升电路的整体性能。实验室仿核脉冲测试及²⁴¹ Am中子源辐照测试表明,该电路可用于碳化硅探测器的核辐射测量。     

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.