4MV静电正离子加速器辐射监测系统

介绍由主控计算机和多个探测通道组成的辐射监测系统,可以对多种辐射的能量、强度、剂量率、剂量及剂量当量进行监测.该系统虽然是为4MV静电正离子加速器辐射监测设计制作的,但同样适用于类似条件的其他场所的辐射监测.     

CMOS摄像头辐射监测系统构建

构建了一套基于CMOS摄像头的辐射监测系统,该系统由CMOS摄像头、数据获取软件两部分构成。利用137Cs源分析了该辐射探测系统对γ、X射线的响应特性,并对该辐射监测系统的灵敏度、稳定性与可靠性等探测性能进行了测试。实验结果表明,该辐射探测方法可有效识别CMOS摄像头所采集图像中的辐射粒子事件,该辐射测量系统所探测到的辐射粒子数量与辐射剂量率呈线性关系,但其灵敏度较低,适合用于高辐射剂量的γ、X辐射监测。     

CPR1000型核电机组厂房辐射监测系统

简要介绍CPR1000型核电机组的厂房辐射监测系统的功能、组成及结构,根据辐射监测通道的测量方式、测量对象与目的的不同对系统的下属辐射监测通道进行了分类介绍。     

航空γ能谱探测人工放射性核素检测限研究

核与辐射航空监测中人工放射性核素探测下限是衡量核与辐射航空监测能力的一个重要指标。基于大体积NaI(Tl)探测器核与辐射航空监测系统、固定翼飞机(Y-12和Y-5飞机)在全国数个不同辐射背景地区不同飞行高度的测量数据,研究航空γ能谱探测人工放射性核素137Cs和60Co探测下限的影响因素。结果表明:随航测高度和航测飞行速度的降低,人工放射性核素的探测下限相应地降低;在同一个航测高度上,探测下限随辐射背景水平而增大;水域上对人工放射性核素的探测下限最低;随人工放射性核素γ射线能量的降低,探测下限反而增大。本次研究为核与辐射航空监测中有效控制影响因素降低人工放射性核素探测下限提供了重要依据。     

BESⅢCsI(T1)晶体量能器LED-光纤监测系统的研究

BESⅢCsI(T1)晶体量能器采用LED-光纤监测系统达到监测晶体探测单元和电子学通道的日常运行和性能变化,并在晶体探测单元制造中的存放,组装和运输等过程中通过快速对照测量,检验每个过程中的质量和可靠性.文章介绍LED-光纤监测系统的设计,研究和性能测量.     

辐射早期报警系统

辐射早期报警系统的原型站已安装于奥地利塞伯斯托夫研究中心。开发这个装置的目的在于探测和跟踪早期的放射性污染所必需的所有相关参数。该站包含以下装置：测量周围γ剂量率的辐射监测通道；测量空气温度和湿度、风向和风速以及降雨量的气象监测通道；数据处理和储存装置。该系统能在恶劣的环境条件下自动运行和获取数据。它通过租用拨号线路、公用电话交换网或通过射频传输与中央处理平台相连接。该远程即使通讯线路中断也可至少连续获取和储存一个月的数据。多个站可以连成一个网，提供每个点上详细的放射性和气象数据。这样可根据当时的局部气象数据的计算结果，发现、跟踪和预报所增加的环境辐射水平。中央处理平台所用的精密软件采用三维弥散计算模式，可提供剂量分布的时间预测景象。     

大亚湾核电厂2KRT007MA故障原因分析及其改进

大亚湾核电厂辐射监视系统(KRT系统)的KRT007MA监测从冷凝器抽出的非冷凝抽取物的β活性,以探测蒸汽发生器的泄漏。由于冷凝器系统的原因,导致KRT007MA采样气体中含有水滴,造成KRT007MA通道频繁发生故障。通过调查分析,确定了故障的根本原因,并采取了针对性的改进措施,彻底解决了问题。     

星载核爆脉冲γ射线及中子监测技术的进展

卫星有效载荷对大气层和太空核爆实施探测、定位和识别是各核大国争相研究的前沿课题.回顾了美国主要监测卫星对核爆脉冲γ射线及中子监测的早期技术,包括天基系统构成、辐射探测器和探测方法,对未来大气层和太空核爆监测技术和装备进行了展望和设想,以期为相关领域的研究提供一定参考.     

上海光源固定辐射监测系统数据库及数据分析软件

SSRF固定辐射监测系统用于监测SSRF运行期间工作区域与周围环境的辐射剂量水平,包括Gamma辐射和中子辐射.监控计算机将数据从前端采集模块中读取,并存在中心管理计算机上的MySQL数据库中.数据分析软件利用Python脚本语言编写,可实现对某特定监测通道的某一时间段的历史数据进行查询、统计、画图及导出等功能,另外,还可对报警事件进行专门查询.查询网页利用PHP语言编写,同一网段的用户可以通过网页对历史数据进行查询和画图.     

基于CAN总线的辐射监测网与以太网接口设计

介绍了基于CAN总线的辐射监测网与以太网接口设计.系统以LPC2294作为核心处理器,DM9000以太网控制器作为以太网主控芯片构建了Ethemet和多路CAN的网关的硬件电路,将CAN总线探测到的数据通过以太网传输到主控中心进行数据图形汇总显示.     

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.