闪光照相X源光斑编码孔成像诊断可行性研究

X源光斑形状和强度分布是高能闪光照相图像反演时必需的定解条件,需高精度的测量,但目前缺少成熟的方法应用于成像时诊断对应的X源光斑。本文通过蒙特卡罗程序直接模拟及图像重建,验证了对有能量和角度分布、有散射等干扰的实际X源,由其编码图像可重建出源的强度空间分布信息,且具有较高精度。采用编码孔成像方法,在闪光照相实验的同时伴随X源光斑的特征检测是可行的,可提高闪光照相图像反演精度。     

高能X射线光机性能研究

X射线光机的管电压、管电流及固有过滤是X射线光机质量控制的重要参数。X射线光机管电压、管电流以及固有过滤的测量,对于X射线光机的性能评价和参考辐射质的建立是非常必要的。以一台管电压上限为600 k V的X射线光机为例,用能谱终点法测量对X射线光机的管电压进行测量,得出X射线光机能在±1%的范围内显示管电压值;用指型电离室PTW30013测量了高能X射线光机管电流的线性及稳定性,在相同的管电压、管电流下,实际测量到的管电流的相对标准偏差在0.097%;分别用半值层法和外推法测量高能X射线光机的固有过滤,两个结果取平均值得到高能X射线光机固有过滤为0.146 mm Al。     

用于高能X射线检测的胶片库设计及防护实验

工业胶片库是固体火箭发动机高能X射线照相检测设备的重要组成部分,为保证其中的胶片不被现场高能X射线曝光,其结构设计上需考虑对高能射线的防护。本文叙述了相关设计原理,并对设计的结构防护性能进行了实验测量,实验表明胶片库能够对高能X射线起到很好的防护作用,符合设计要求。     

NaI晶体谱仪采集X射线能谱测量方法研究

为准确测量轫致辐射X射线能谱,利用NaI晶体谱仪对于测量光子的能谱展宽效应,结合理论模拟分析,提出了采用变能量矩阵求解法实现X射线能谱的重建。该方法通过合理选择能量区间,可有效消除能谱响应矩阵中各矢量的相关性,从而实现能谱的准确重建。并分别以均匀能谱分布和实际轫致辐射X射线能谱为例,进行了X射线的能谱重建。获得结果与原始能谱的相关性约为0.98。     

一体化高能X射线参数测量装置设计及应用

研制了一体化高能X射线参数测量装置,一次测量中可同时获得X射线源的能谱、焦斑尺寸、强度分布及照射量的角分布.通过方孔编码成像方法获得X射线源的焦斑尺寸及强度分布;采用螺旋楔形法获得轫致辐射能谱;利用热释光剂量片测得照射量的角分布.使用该装置在流体物理研究所12 MeVLIA及神龙一号两台直线感应加速器上分别进行了X射线...     

a-Si FPD在闪光X光照相中的应用可行性实验研究

非晶硅平板探测器(a-Si Flat Panel Detector)已在无损检测、医疗领域的连续式X光照相中得到了广泛应用,但在脉冲式(ns量级)闪光X光照相中的应用可行性及成像性能却未见报导.本文利用Varian公司生产的PaxScan 2520 HE型非晶硅平板探测器为接收系统,在450keV脉冲X光机上开展了闪光照相实验,考察了该探测器的应用可行性,测量了其探测灵敏度、像质计灵敏度、线扩散函数(LSF)及调制传递函数(MTF).实验结果表明该探测器可应用于闪光X光照相,且探测灵敏度较高,空间分辨率较好,是一种有前景的闪光X光照相图像接收系统.     

X射线管原始谱和透射谱的测量及应用

本文基于COMET公司MXR225/22型X射线管,使用高纯锗探测器测量了X射线管大、小焦点几种管电压的X射线原始谱,并测量了小焦点下的初始透射谱,在此基础上测量了X射线穿过几种不同材质(铝、钛、铁和铜)吸收片的透射谱。结果表明：X射线管大、小焦点能谱近似相同,低能端X射线比重较大,原始谱中包含铜、银、钨和铅元素的特征峰;初始透射谱低能端硬化明显,并随着管电压升高,高能端所占比重增大,钨特征峰变得明显,X射线平均能量升高,能谱的X射线强度最大区域在最高能量的1/3附近;金属吸收片对X射线硬化明显,硬化效果强烈依赖于其原子序数。相关结果已在工业CT硬化校正中应用,重建图像质量得到改善。     

A Particles' Direction Detector on Manned Space Ⅱ

针对空间带电粒子各向异性分布,不同的入射方向,粒子的通量有数个量级的差异,提出安装在二期载人航天目标飞行器上的新一代空间粒子探测器——空间粒子方向探测器.该仪器为我国最新研制的多功能、小型化空间带电粒子探测器,首次实现了高能电子、质子能谱探测及180°方向的粒子通量测量.通过监测轨道空间各种带电粒子的区域分布、方向分布和能谱分布,以及时空变化,从而获得完整的空间高能带电粒子的辐射图像,建立载人航天轨道静态和初步动态粒子辐射模型.     

针孔照相技术在核探测中的应用

利用各种相机拍摄可见光源的静态或动态照片是一种很容易的事,但拍摄不可见光源(如核辐射源)的照片就不是那么容易了。随着科学技术的发展,近10年来,在国内外核探测技术中发展一种针孔照相技术,用以获得X射线、γ射线和中子强度的空间分布、时间谱和能谱等,为受控热核反应、核反应堆、高温等离子体等方面的研究提供一种诊断方法。近年来,我们在针孔照相技术方面做了一些探索性工作,研制出一套针孔照相系统,并利用这套装置对X辐射源进行了初步研究。拍摄到X辐射源的照片,仅供参考。     

X射线荧光分析原级能谱分布的MCNP模拟

X射线荧光分析中,入射激发能谱是影响元素特征荧光强度大小的直接因素。本文使用MCNP程序模拟不同条件下电子打靶后的X射线能谱分布,计算结果能够反映不同条件下特征谱线和连续谱线的特点。模拟能谱数据可用于X射线荧光分析的数据处理。     

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.