Ladu计数器性能研究

测量了角响应、径向微分响应、能量响应及球腔内中子计数率分布,并估算了有效中心。角响应小于5%,径向微分响应与实心球探测器的情况相同。在源距大于5倍计数器半径的情况下,忽略有效中心与几何中心之差异所导入的响应值误差小于0.7％。球腔内超热与热中子计数比小于10％,计数率依赖于热中子探测器所在位置。大约在200eV至5MeV能区,能量响应是平伸的,误差小于±18％。     

蒙特卡罗模拟确定HPGe探测器点源效率函数及参数

在探测器晶体体积一定的情况下,HPGe探测器点源效率主要由γ射线能量、角度和探测距决定。利用极坐标对点源进行空间定位,试验测试了不同角度和探测距条件下137Cs和60Co点源的γ能谱,同时采用MCNP程序模拟计算HPGe探测器不同角度与探测距条件下γ点源效率,并与实验值进行对比和校正。结果表明,探测角度在0-9π/24,γ点源效率模拟值与实验值之间全能峰净计数的相对偏差均在8%以内。最后对γ点源效率模拟值进行多元非线性回归,确定了在特征γ射线能量下,以角度和探测距为因变量的点源效率函数及其参数。     

点源模型刻度就地谱仪角度修正因子影响研究

对于核与辐射事故应急,就地谱仪现场监测辐射事故污染的程度和范围,利于现场指挥快速科学决策。应急准备的一项重要工作是就地谱仪准确校准角度修正因子及其相对偏差及其海拔高度适宜性。采用MCNP模拟计算和试验校准,建立一种就地P型高纯锗谱仪探测器模型。根据就地谱仪校准角度修正因子的点源模型,理论计算其初级γ射线注量率和MCNP模拟计算探测器高度1 m、2 m、3 m、11种入射角和11种γ能量的点源探测效率,以及500 m、2 261 m、3 650 m海拔高度,探测器高度1 m、11种入射角、3种γ能量的点源探测效率和初级γ射线注量率,进而分析其角响应因子、角度修正因子和相对标准偏差。研究结果表明,点源距离大于1 m情况下,其角响应因子和角度修正因子相对标准偏差小于4.35%;海拔高度500～3 650 m情况下,其角响应因子和角度修正因子相对标准偏差小于1.2%;其角度修正因子是能量的自然对数的分段函数,在120～3 000 keV为线性函数,在45～120 keV为指数函数。     

溴化镧探测器的晶体表征与全能峰效率计算

无源效率刻度技术已在辐射探测器的效率刻度中得到了广泛的应用。本文基于点源效率实验及蒙特卡罗模拟计算方法,对溴化镧探测器的晶体尺寸进行了调整;在此基础上,计算得到不同位置处全能峰效率的计算值。点源效率实验的验证结果表明,在121～1 332 keV能量范围内,γ光子全能峰效率的计算值与实验值的相对偏差小于±5%。     

~(220)Rn子体γ能谱测量中LaBr_3γ谱仪探测效率刻度

基于标准点源(~(60)Co、~(137)Cs)测量与MC模拟计算,对LaBr_3探测器的结构尺寸进行了优化,并通过模拟计算获得了La Br3探测器对~(222)Rn/~(220)Rn子体采样滤膜的探测效率。~(222)Rn子体滤膜源效率实验验证表明,LaBr_3探测器对~(222)Rn/~(220)Rn子体采样滤膜的探测效率模拟值与实际值的相对误差在3%以内。该研究结果为实现~(220)Rn子体的γ能谱准确测量打下了基础。     

LaBr_3:Ce探测器对低能γ射线角响应研究

建立以探测器前表面中心和探测器体心为参考原点的两种几何模型,研究了Saint-Gobain Brillan Ce380探测器对~(241)Am、~(133)Ba、~(137)Cs源γ射线在15 cm、25 cm、35 cm处由0~90°范围内入射能量沉积脉冲高度谱,通过源峰探测效率的差异表征角响应的变化。实验结果表明:该探测器对低能γ射线响应随入射角度的增大呈递减趋势,源峰探测效率最大变化约达30%,并随源距离的增加各向异性程度逐渐减弱。此结果可为LaBr_3:Ce探测器检测未知核材料及其剂量水平提供修正参考。     

平板高纯锗探测器几何参数修正的解析方法

本文推导了1个用于计算平板高纯锗探测器对点源发射光子的探测效率的数值积分公式,并应用此积分公式进行了高纯锗探测器的几何参数修正。将²⁴¹Am、¹³⁷Cs点源分别置于平板探测器前端的不同距离（1~20 cm）处进行实验测量,以探测效率的实验结果为拟合真值,利用积分公式通过加权最小二乘拟合获得该探测器的几何参数。将修正后的参数应用于MCNP模拟计算,对59.5及661.6 keV光子,在1~20 cm探测距离范围内,探测效率的模拟值与实验值之间的相对偏差<1%。研究表明,此解析方法实现了对探测器几何参数的快速修正,结果准确可靠。     

球形快中子监测器

本文描述一种由置于聚乙烯球腔内的慢中子探测器而组成的快中子监测器。聚乙烯球分为两个半球,外径为24.4厘米,厚度为6.2厘米,密度为0.92克/厘米~3,外包厚度为0.2厘米的两个镉制半球壳。中子能量在0.02～5兆电子伏之间,以BF_3计数器和~(235)U涤纶膜固体径迹探测器为中心探测器时,监测器的灵敏度在±15%和±12%以内为常数,其值为2.03计数/中子/厘米~2和1.13×10~(-6)径迹/中子;在15兆电子伏处,灵敏度下降约40%。源距大于80厘米,监测器的响应与距离的关系服从反平方律。监测器的角响应优于90%。该监测器可用于直接读数和累积读数。     

应用蒙特卡罗方法确定NaI探测器的点源效率函数及其参数

为了探讨NaIγ探测器对点状γ射线源(以下简称"点源")的探测效率与点源空间位置之间的关系,采用蒙特卡罗方法通用程序模拟计算了NaIγ探测器对空间不同位置处137Cs、60Co点源的探测效率.根据模拟计算结果,通过数值拟合方法,确定了NaI探测器对点源的探测效率函数及其参数.研究表明,应用蒙特卡罗模拟方法确定NaIγ探测器对于点源的探测效率函数及其参数是一种简便、有效的方法.     

中子活化分析参量化的进一步研究——Ⅳ.K_0法中子活化分析中级联γ符合效应的参量法校正

研究了Ge探测器近几何测量时,级联和跨越γ射线全能峰效率的符合效应校正方法。首次指出,总响应应包括探测器周围物质的散射贡献,修正了传统的总响应定义,并证明峰/总比(P/T)与源-探测器距离有关。在此基础上,测定了两个Ge探测器在不同几何下的P/T,并实用于K_0法中子活化分析中的级联γ符合校正。还举例说明了本法的准确性、编制了中子活化分析指示核素主要分析线的级联符合校正用参数表。     

Identification of radiation treatment of wheat （Triticum aestivum. L）and rice （Oryza sativa. L） samples using thermoluminescence of contaminating minerals

Food irradiation is gaining popularity worldwide and this technology is important to improve quality and reduce the post harvest losses of food. Because of the rapid commercialization of irradiated foods throughout the world, compliance of different regulations relating to use of technology in different countries and demand of consumers for clear labelling of irradiated foods, there is need for the development of analytical methods to detect radiation treatment of food. Among several methods studied so far, thermoluminescence （TL） is an important method that can be used to find out the irradiation history of food that contain even a very minute amount of dust particles. In this study, the irradiated and unirradiated wheat and rice samples were analyzed using the TL method. The samples were purchased from the local market of Peshawar and irradiated to radiation doses of 0.5 and 1.0 kGy using Co-60 gamma irradiator at the Nuclear Institute for Food and Agriculture （NIFA）, Peshawar. The mineral contaminants were isolated by jet water, ultrasonic treatment, and density gradient. TL glow curves of the isolated minerals from irradiated and unirradiated samples were recorded between the temperature ranges of 50-500℃ using a TL reader. Generally, the glow curves for irradiated samples showed much higher TL intensities （TL1） than the unirradiated samples. The results were normalized by rerradiation of mineral samples to gamma-ray dose of 1.0 kGy followed by determination of the second glow curves （TL2）. The ratio of the area of first glow curve to that of second glow curve （TL1/TL2） was calculated for selected temperature intervals and compared with the recommended values for unirradiated and irradiated samples. Finally, the shapes of the glow curves for irradiated and unirradiated samples were also analyzed. On the basis of these results （comparison of TL-intensities, TL1/TL2 ratios and shapes of the glow curves）, all the irradiated and unirradiated samples of wheat and rice were unequivocally identified.     

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.     

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。     

The preclinical pharmacological study of dopamine transporter imaging agent 18F-FP-β-CIT

The paper is to study pharmacologic characteristics of 18F-FP-β-CIT (18F-N-(3-fluoropropyl)-2β- carbomethoxy-3β- (4-iodophenyl)nortropane) as an imaging agent for dopamine transporter. The radiochemical purity of 18F-FP-β-CIT in aqueous solution was over 95% after standing at room temperature for 4h. Biodistribution displayed rapid uptake in rat brain (1.375 %ID/organ at 5min and 0.100 %ID/organ at 180 min) and the striatal uptake was 1.444,0.731, 0.397, 0.230 and 0.146 %ID/g at 5, 30, 60, 120 and 180 min, respectively. The values of striatum/cerebellum,striatum/frontal cortex and striatum / hippocampus in rat's brain at 30 min were 3.38, 2.17 and 2.40 respectively. The uptake in striatum can be blocked by β-CFT, suggesting that 18F-FP-β-CIT binds to DAT peculiarly. The compound was rapidly cleared from monkey's blood. The striatal uptake was bilaterally decreased in the left-sided lesioned PD rats, compared with normal control. Brain PET imaging studies in normal monkey showed that 18F-FP-β-CIT was concentrated in striatum. The test of undue toxicity showed that the dose received by mice was 1250 times as by human, which indicates that 18F-FP-β-CIT is very safe. So 18F-FP-β-CIT is a promising PET imaging agent for DAT with safety and validity.     

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.     

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.     

PLASMA SCIENCE AND TECHNOLOGY AUTHOR INDEX TO VOLUME 16(2014)

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Radioactivity levels in soil of salt field area,Kelambakkam,Tamilnadu,India

Soil samples in and around salt field area have been analyzed for natural radioactivity concentration using gamma ray spectrometer.The activity concentration for ~(232)Th,~(238)U and ~(40)K are ranged from 27.88 to 45.27 Bq/kg, from BDL to 13.30 Bq/kg,and from 135.54 to 381.28 Bq/kg,respectively.The measured activity concentrations for these radionuclides were compared with world average activity of soil.The average activity concentration of ~(232)Th in the present study is 1.19 times higher than world median value while the activity of ~(238)U and ~(40)K is found to be lower. The absorbed dose rates due to these radionuclides were calculated.The average absorbed gamma dose rate due to the presence of ~(232)Th,~(238)U and ~(40)K in soil samples is 36.99 nGy·h~(-1).These results indicate no radiological anomaly. The data presented in this study will serve as a base line survey for primordial radionuclides concentration in the study area.     

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.