一种新型中子剂量当量仪的电子学系统设计

介绍了一种新型中子剂量当量仪的电子学系统的设计,该系统由电源电路、放大器电路、脉冲幅度甄别电路和仪器控制电路等部分组成.该系统能够满足该新型中子剂量仪的功能要求,能够实现该新型中子剂量仪的信号采集、结果计算和仪表控制等功能.     

BH3105E型中子剂量当量仪研制

研制成功BH3105E型中子剂量当量仪.仪器采用镉吸收棒法实现热中子至14 MeV区间等剂量当量测量;选用6Li玻璃闪烁体作为中子探测器;探头输出信号送至硬件电路进行处理.信号经主放大器、脉冲幅度甄别器、整形器由处理器进行计数采集.仪器系统软件设计实现了测量数据存储,采用串口协议与单片机进行通讯.     

SDM2000半导体个人剂量仪探测器实验及测量电路研制

介绍了SDM2000个人剂量仪探测器实验及其测量电路的研制。从探测器的物理特性、工作电压、工艺等方面,对PIN光敏二极管和化合物半导体探测器进行了对比,得出了PIN光敏二极管的特点适合于个人剂量仪的结论,并进一步对PIN光敏二极管测量电路各部分包括电荷灵敏放大器、两级主放大器、脉冲幅度甄别器及DC DC电源电路的电路设计原理、使用的集成运算放大器、电路板工艺设计、主要性能指标等方面分别做了较为详细的阐述。结合SDM2000个人剂量仪使用的PIN光敏二极管探测器和其实用测量电路,通过测量和实验,给出了SDM2000个人剂量仪主要物理特性和主要性能指标。     

高分辨粉末衍射仪数据采集系统研制

介绍了中国先进研究堆(CARR)旁高分辨粉末衍射仪数据采集系统的整体设计和硬件组成,阐述了各单元电路的结构和设计。加载输入信号对电路进行了调试,测试了电路的各项性能,测试结果满足设计要求。从探测器、前置放大器、主放大器、甄别器、计数卡到计算机的整个系统,实现了对信号的获取、放大、滤波成形、甄别、定标计数和存储全过程,多达65路的数据采集系统已研制成功。     

基于脉冲幅度谱的3He正比计数管 中子散射谱仪探测系统关键参数测定方法

中子散射谱仪探测系统各部件性能参数需相互匹配,准确的参数测定方法利于改进谱仪探测系统的实际性能,提高物理实验数据质量(可信度等).本文基于3 He正比计数管中子散射谱仪探测系统,开发了脉冲幅度甄别器甄别阈、核辐射探测器工作电压以及气体核辐射探测器性能参数的脉冲幅度谱测定方法,这些方法较传统的积分曲线测定方法、坪曲线测定...     

16通道nToF放大定时甄别器

本文介绍了-个用于ICF实验的中子飞行时间测量的16通道放大定时甄别器(ATD),其主要功能是将闪烁探测器输出的信号进行缓冲放大,并进行成形和时间甄别,送到后面的时间测量和幅度测量系统.     

有机闪烁体探测器数字化信号处理电路设计

介绍了基于FPGA的有机闪烁体探测器数字化信号处理电路的设计。电路设计由前置放大器、高速ADC、FPGA系统、MCU微控制系统、电源系统等组成,通过对粒子射线的模拟信号采集、后续分析处理和脉冲形状算法,实现中子和γ脉冲信号的甄别及对应剂量值的计算。主要性能测试结果表明:电路设计具有较好的中子和γ甄别效果,可实现准确有效的中子和γ剂量测量。     

反应堆中子注量率相对分布测量装置中多通道放大甄别器研制

为了测量反应堆内中子注量率分布,保证反应堆内活化 55 Mn- 58 Ni合金探测片γ计数测量的可靠性,本文研制了中子注量率分布测量装置中9通道放大甄别器。多通道放大甄别器性能指标测试与应用测试结果表明：每个通道放大器增益1～21连续可调、甄别器阈值独立连续可调,具有最大计数率高、灵敏度高、稳定性好、系统抗串扰能力强等优点;放大器增益长期稳定性≤1%,甄别器最小输入脉冲宽度≥ 0.1 μs,甄别器最大计数率≤4×10 6 s -1,能用于实时长期稳定测量反应堆内中子注量率分布。     

3 启明星1#次临界装置上第1阶段实验研究

在启明星1#次临界装置设计、加工过程中，先后建立在线、瞬时响应的测量仪器一次临界反应堆多时空动态测量系统，该系统包括16个^3He探测器及其前置放大器、16个主放大器、16个甄别成型单道及1台16通道同时信号采集和分析器，可测量ADS启明星次临界实验平台对加速器束流的瞬时响应。     

线性脉冲放大器

提出了一种微型成形放大器和门积分器和门积分,简要介绍了电路结构与电路设计,工作原理及技术指标。该电路主要用于半导体探测器,正比计数器,闪烁探测器等仪器输出信号的放大,成形和多道脉冲幅度分析器等仪器的采样,保持电路的分析与研究。     

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.