用效率外推法测~(131)I和~(198)Au绝对强度

用4πβ-γ符合吸收曲线效率外推法,测定短寿命的医用同位素~(131)I、~(198)Au绝对强度。测量结果分别对本底、死时间、分辨时间进行了修正,同时还考虑了短半衰期引起的修正。对~(131)I和~(198)Au的最大测量误差分别为0.57％和1.7％。本装置稍作改变后,还测量了具有电子俘获衰变的核素。     

γ探测死时间与计数修正因子的关系

为在γ放射性活度很大的测量中使测量系统得到更好的准确度,本文使用干扰源研究HPGe探测器得到了测量系统死时间与计数损失的关系。在γ能量为0.3~1.3 MeV时进行实验,使用104~105 Bq量级的放射源,修正能峰的计数率一般保持在几十s-1,证明在误差范围(3%)内,计数损失随死时间变化的关系与射线能量和计数强度无关,任意强度的任意核素均可使用这一修正公式进行计数损失修正。     

肺部计数器虚拟校准结果的影响因素

内照射活体测量中,肺部计数器通常忽略肺以外其他器官中沉积的放射性核素对探测器计数的贡献,且校准使用的参考体模和被监测人之间会有身体形态的差异。本文利用中国成年男性体模库,采用蒙特卡罗程序模拟计算了~(65)Zn和~(60)Co核素的器官源探测效率,并计算了总探测效率,研究了这两个因素对虚拟校准的影响。结果表明,对于类似65Zn的核素不能忽略肺部以外其他器官源的计数贡献;同一身高下,肺部计数器对~(65)Zn和~(60)Co核素的总探测效率随体重增加而降低,且对于65Zn核素的降低比例会随摄入时间而变化;对于同一体模的总探测效率会随时间而降低。由此证明,核素生物动力学分布和体模形态的差异对肺部计数器总探测效率均有较大影响,且对不同核素影响会有不同。     

基于Geant4的肺部计数器效率校准及其受核素分布影响研究

效率校准是人体内照射活体监测中的一个关键环节,是影响内污染活体测量准确性的一个重要因素。利用人体躯干物理模型的CT扫描图片和实验确定的探测器晶体尺寸,分别建立了三维人体数字模型和高纯锗探测器的计算模型,进而通过调用Geant4工具包,编写了模拟肺部计数器的蒙特卡罗程序,用以校准计数器效率。在此基础上,结合ICRP生物动力学模型,模拟计算全身其他器官滞留核素对肺部计数器计数的贡献,研究核素在其他器官的分布对计数器效率的影响。结果表明:肺部计数器效率的蒙特卡罗校准结果与实验测量结果相对偏差为2.47%(对59.5 ke V)和-8.58%(对17.5 ke V);在摄入核素241Am的最初2天内和50天后,人体的实际探测效率要高于只考虑肺部滞留的探测效率,在其他器官分布的核素在肺部计数器的计数占总计数的60%以上,而在摄入中期(第3—50天),二者结果较为一致,AMAD为1μm时,其他器官内核素的计数小于20%,AMAD为5μm时,其他器官内核素的计数在30%以内。     

131I和134Cs核的衰变研究

~(131)I是一个短寿命核素,它的半衰期仅有8.02 d,但是这个核素在医学等领域内有广泛的用途,在80—475 keV能区内有七条较强的γ射线可用来刻度Ge探测器的效率。~(134)Cs有较长的寿命(T(1/2)=745.2 d),它在475—1400 keV能区内发射十条较强的γ射线,它和~(131)I合用在80—1400 keV能区可作为标准源刻度Ge探测器效率。一些作者已研究过这两个核素。本工作的目的是精确测定相对γ线发射几率和对一些较强级联γ射线作符合计数修正。     

89Rb半衰期测量

⁸⁹Rb是重要的裂变产物核素,半衰期是其一项非常重要的核参数。本文采用参考源法,运用双HPGe探头距离接续测定了⁸⁹Rb的半衰期。参考源法利用待测源和参考源的γ射线全能峰之比消除了测量过程中死时间和脉冲堆积带来的计数修正影响。由于⁸⁹Rb半衰期较短,数据分析运用了半衰期迭代法,并用平移法归一探头测量数据,最终实验测得⁸⁹Rb半衰期为（14.41±0.04） min。     

快速分离技术及其应用

迄今为止,在已知的二千多个放射性核素中,几乎有二分之一是半衰期不到十分钟的短寿命核素。它们在核科学中具有很重要的研究价值。随着现代科学的发展,人们对于短寿命核素的研究日益感到兴趣。在重离子反应、高能散裂反应、超重元素的合成和研究、短寿命放射性核素生产等领域中,重点研究对象都是半衰期较短的核素。人们经常需要对特定核素进行化学性质的鉴定和基本核参数的测定。对于这类研究对象,普通放射化学分离法已无能为力,而快速分离技术正是为了满足短寿命核素研究的特殊需要而发展起来的新技术。由于它具有分离速度快、选择性高的优点,能从辐照靶子的混合核素中有效地分离出各种短寿命核素,因而获得了广泛的应用。     

循环带传输系统

针对短半衰期核素实验研究的特点,设计了一套新的收集和测量带系统,此系统采用低负载以及循环带结构,从而缩短了传输所需时间,大幅减少了收集带的更换频率.使之可以用于半衰期在0.2s以上的短半衰期核素的研究.     

熔岩玻璃体核素衰变热功率的计算

温度是影响熔岩玻璃体溶解速度的关键因素,为此,本文计算了核试验后10~300 000d内熔岩玻璃体中核素衰变热功率,评估了核素衰变热功率对熔岩玻璃体的温度和溶解速度的影响程度。采用了国际原子能机构给出的100kt TNT当量地下核试验产生的、半衰期大于1a的放射性核素含量,利用其中裂变产物核素137 Cs的含量推算累积裂变产额大于0.1%、半衰期为1d~1a的短寿命裂变产物核素的含量。分析了各核素的放射性衰变特点,采用ENDF/BⅦ库中核素衰变辐射的平均α能量、平均电子能量和平均电磁辐射能量计算各核素在熔岩玻璃体内因衰变而沉积的能量。计算结果表明:核素衰变热功率呈分段幂函数衰减;在10~2 000d、2 000~60 000d和60 000d之后的时段内,衰变热功率分别主要源于短寿命裂变产物核素、长寿命裂变产物核素和锕系元素。核素衰变热功率对熔岩玻璃体的温度和溶解速度的影响不大,1 000d后影响非常小。     

87Kr活度测量中干扰核素的扣除

用内充气正比计数管测量短寿命核素87Kr活度中,存在气体核素85mKr和125Xe的干扰,且在制源过程中无法将杂质核素分离出去.根据各核素半衰期不同的特点,对样品进行跟踪测量,用加权最小二乘法求解线性方程组的系数对干扰气体进行了扣除,准确测量了87Kr的活度.     

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.