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的高速核信号采集系统设计

描述了一种基于现场可编程逻辑阵列(FPGA)的高速核信号采集系统的设计方案.FPGA作为控制核心,实现对高速Analog - to - Digital Converter(ADC)和Universal Serial Bus( USB)的逻辑控制和数字信号的采样、滤波、甄别、存储、传输处理,并使用异步First In First Out(FIFO)实现ADC数据采集模块和USB数据传输模块2个不同时钟域之间的数据传输,提高数据的吞吐率.最后利用上位机软件进行数据处理和绘图显示.测试结果表明,该系统能够实现核信号的实时、高效采集.     

基于FPGA的核信号高速采集系统的设计

对核信号高速采集系统的研究可实现数字核信号处理方法的改进与算法的验证,以及对数字化核能谱测量系统性能指标的提升具有重要意义。研发一套核信号高速采集系统,通过高速ADC将信号调理电路输出核脉冲信号进行采样,同时在FPGA系统中实现FIFO、USB接口传输功能,将采样后的数据经过FIFO缓存,再通过USB接口传送给后续计算机系统进行保存、显示与进一步处理。在搭建的核信号采集系统上进行测试,通过对5、10、20与33.3 MHz采样率下得到的核信号进行分析与讨论,表明该系统可有效地实现核信号的高速采集。     

基于USB和FPGA的多功能数据采集系统

设计并实现了一种基于USB接口的多功能数据采集系统。该系统支持4路模拟信号输入,通过高速ADC进行采样,数字化后的数据由FPGA进行处理,可实现波形采样、脉冲计数、多道脉冲幅度分析、电荷分配法信号读出等功能。下位机硬件和PC通过USB接口通信,上位机软件采用Labview编写,负责初始化硬件以及参数配置,读取采集数据并进行数据在线处理以及结果的实时显示。     

基于FPGA的数字核信号处理系统的研究

核能谱是核物理研究、射线探测和核技术应用领域中获取的重要信息,对其测量技术的改进一直为热点研究问题。论文基于FPGA设计一套数字核信号处理系统,对高速ADC采样后的数字核信号通过FPGA控制的高速USB接口电路,直接传送给计算机的测试平台以实现核信号的离线处理,同时该数字核信号在FPGA中实现其滤波成形、堆积识别,基线恢复等功能,得到的能谱通过USB接口传送给计算机。通过测试,系统既能实现原始核信号的传输与保存,又能实现数字核信号的在线处理。     

基于大学核物理实验的数字化MCA的研制

介绍了一种用于大学核物理教学实验的基于FPGA全数字化多道脉冲幅度分析器(MCA)的研制。系统采用全数字化方法对输入的脉冲信号高速数字化,然后送入FPGA进行数字寻峰、记录、谱处理,并在主机上显示。给出了数字寻峰的原理,利用双甄别阈值提高系统的抗干扰能力;针对ADC的非线性对系统造成的影响,研究修正算法,保证数据采样的道宽均匀性;鉴于MCA采样存储的数据量大的特点,采用双RAM并行工作方式,将传输数据和计数存储分开处理,减少死时间及数据的溢出;在终端显示方面,主机通过USB总线实现了系统实时监控和能谱数据传输。通过实验对比了该系统与商用MCA的性能,取得了很好的测试效果。     

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。     

高速核脉冲信号数字存储示波器的研制

针对核脉冲信号数字化处理的研究需求及当前示波器的应用限制,以高速FPGA系统为核心,采用80 M高速ADC、信号调理电路和USB接口,设计了高速核脉冲信号采集器。通过PC机上编写的软件完成设置、采集数据的接收、显示和存储。设计了双触发模式,从而实现对核脉冲信号的两种采集保存方法,以便于对核脉冲信号的后续处理和研究。测试表明:该设计能够高速、准确地进行核脉冲信号的采集、显示和储存。     

GEM探测器读出电子学ADC采样系统设计

本文简要介绍了GEM探测器读出电子学ADC采样系统设计与测试。该系统包括模数变换模块、数据汇总模块和后端数据接收模块三部分。本文详细介绍了模数变换模块硬件电路设计、FPGA逻辑设计、光纤数据传输设计以及ADC采样芯片的测试方法。经过测试,该系统实现了8通道数据实时采集、传输、存储及显示功能。     

基于FPGA的核信号采集主控系统设计

介绍了以FPGA为控制核心的核信号采集主控系统的设计。FPGA内实现的功能包括与计算机的通信,对ADC采样的控制,对采样信号的数字甄别、存储等。可在线对阈值及ADC的寄存器进行设置。整个控制系统包括存储器(FIFO)在一片FPGA内实现,系统硬件结构简单,能有效地提升核分析仪器的性能并有利于其小型化。     

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.