通用数字核谱仪系统设计

设计一套基于高速ADC+FPGA+ARM的通用型数字核谱仪系统,对探测器系统输出的信号经过信号调理系统后,采用高速、高分辨率ADC进行采样,将采样后的核信号传输给由FPGA与ARM搭建的数字核信号处理系统,采样梯形成形对核脉冲信号进行处理,最后得到的能谱通过USB接口传送给计算机系统进行显示、存储以及进一步处理。通过Si-PIN探测器对Fe的X射线能谱,Na I探测器对¹³⁷Cs的γ射线能谱测量的测试,获取能量分辨率分别为178e V与7.2%,表明该系统能有效地实现数字核谱仪系统中核信号调理,高速采集以及数字核信号处理功能的同时,可得到较理想的性能指标。     

基于FPGA的数字核谱仪中高速数字采集技术研究

数字核谱仪的高速实时数据采集能够对数字核谱仪中关键算法的调试起到关键作用。本设计以ALTERA公司的EP2C8T144C6现场可编程门阵列与高速USB数据采集芯片FT2232H为核心,设计并制作了USB高速数据采集系统,可以实现USB接口高速数据传输。核谱仪采集到的信号送入到FPGA中,经过内部FIFO存储器的缓存及算法处理,最后通过USB控制器将信号传输到计算机中,存储并显示出来。设计实现了28MByte/s以上的数据传输率,具有数据传输速度快,准确性高的特点,为进一步实现数字核谱仪高速信号采集奠定了基础。     

基于FPGA+DSP的核信号数字时间谱仪设计

针对核电子学中核脉冲信号的高速实时数字化处理,设计了基于FPGA+DSP的两通道核信号数字时间谱仪。该实验平台基于数字恒比定时(dCFD)原理,采用高速运放和ADC进行模拟信号成型采样,数字信号送入FPGA完成波形判选、数据缓冲、FIR滤波和基线恢复,利用DSP实时信号重构和函数定时,通过USB2.0接口与上位机通信。该系统的主要特点是具有模数电路的高度集成、数字信号的实时运算,接近模拟定时的精度。     

基于FPGA的在线式海水γ谱仪研制

针对监测海水中放射性核素活度浓度极低的需求,研制了一种监测海水中放射性活度的γ谱仪。研制中,利用FPGA技术实现了γ谱仪的低功耗和数字化,并具有弱脉冲信号处理、数字采样、堆积判断等功能。实验测试表明:该γ谱仪具有对海水中放射性核素定量分析测量的能力,达到设计要求。     

核脉冲信号数字化梯形滤波仿真与测试

为了提高数字γ谱仪的能谱分辨率,研究了梯形成形滤波算法。在MATLAB/Simulink开发环境下,采用系统模型开发工具System Generator,完成了核脉冲信号数字化梯形滤波算法的建模,并采用Xilinx公司的ISE开发工具对系统模型自动生成硬件代码(HDL代码)和硬件测试代码进行硬件仿真,验证了硬件代码其正确性。该方法大大简化了FPGA的开发流程,降低了FPGA的开发难度。     

一种新型数字X荧光仪的研制

介绍了一种基于FPGA技术的新型数字X荧光谱仪的实现。阐述了半导体探测器、精密信号放大和高速数据采集等模块电路的设计。重点阐述了在FPGA内部实现数字脉冲成形、峰值判别和多道幅度分析等数字处理的技术细节。整个系统的分析软件基于Visual C++6.0开发环境,采用C++编程语言实现。经过实际测试,系统在能量分辨率和脉冲计数率等主要技术指标上获得了满意的效果。     

基于基线自动恢复技术的数字多道能谱仪

不同放射性强度的测量应用中,探测器输出核脉冲信号的基线将发生漂移,进而造成多道能谱仪的谱线漂移和能量分辨率损失。尽管采用数字基线估计方法可以对核脉冲信号的基线进行正确估计,但纯数字基线恢复算法无法有效处理核脉冲信号基线漂移对前端电路的影响。采用最小平均值基线估计方法,先在现场可编程门阵列(Field-Programmable Gate Array,FPGA)中进行数字基线估计;然后通过SPI总线将基线估计值传入微控制器(Micro-Controller Unit,MCU),MCU根据基线值判断是否进行基线调节,将基线估计值传入数模转换器(Digital-to-analog Converter,DAC);最后在前端电路中实现核脉冲信号的基线恢复。基于La Br3(Ce)探测器的测试结果表明:采用该基线自动恢复技术的数字化多道能谱仪能够实现核脉冲信号的基线自动恢复。在高放射性测量条件下,测量系统能够解决因基线漂移引起的谱线漂移问题,使系统能量分辨率保持稳定。     

基于DSP builder与FPGA的数字脉冲处理算法研究

研究了基于DSP builder与FPGA的数字脉冲处理算法,设计了一种基于数字脉冲处理技术的数字实时时间谱仪。谱仪数字恒比定时(dCFD)算法部分最终全部在FPGA中实现,简化了电路。并组建了一套测量22Na放射源的数字化正电子符合谱仪,对其进行测量得到该系统能量分辨达到3.90%,时间分辨达到157.6 ps,高于传统TDC测得的时间分辨率。     

基于FPGA的全谱岩性密度数据采集系统

设计了一种基于FPGA(现场可编程逻辑器件)的全谱岩性密度数据采集系统,该系统能够在测井过程中对核脉冲信号进行全谱采集,可形成完整谱图,提供更多的地层信息,满足用户需要.该系统基于FPGA设计,用于数据采集和数据处理.为保证探测精度设计了脉冲调理电路,同时配合使用高速AD进行数字量化,采用双端口RAM技术保证数据传输的实时性.通过Modelsim仿真和板级测试,系统测得谱图准确,运行稳定,可广泛应用于生产测井.     

基于交叉采样技术的多道脉冲幅度分析仪设计

为提高核脉冲信号幅度分析精度,本文设计的多道脉冲幅度分析仪采用多片AD7626交叉采样方式提高系统的实时采样率,弥补单片ADC芯片低采样率的不足;使用时钟分配芯片AD9522为时间交叉采样提供精确的转换时钟;FPGA上构建SOPC系统和各功能模块实现时间交叉采样的控制、数字信号读取重组以及脉冲幅度数字化分析处理。通过对设计的多道脉冲幅度分析仪进行谱线采集测试,结果表明其可应用于伽玛能谱测量领域。     

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.