2 高纯锗γ谱仪对土壤效率刻度的蒙特卡罗计算

便携式高纯锗γ谱仪用于核应急工作，为了能更充分地利用该谱仪，对其进行了实验室谱仪改装，将谱仪探头从铅室的顶端置入。改装后可使用谱仪进行实验室分析工作，在发生辐射事故时可很容易地将谱仪从铅室取下来，携带到现场进行测量。     

通用高纯锗γ－X谱仪系统通过部级鉴定

通用高纯锗γ－Ｘ谱仪系统通过部级鉴定由核技术应用所研制的“通用高纯锗γ－Ｘ谱仪系统”通过了部级鉴定。对２套谱仪系统性能进行的现场测试表明：测试结果好于美国同类商品谱仪的性能指标。该谱仪适用于核物理、放射化学与核化学研究，中子活化分析，放射性同位素活度...     

中子反射谱仪的模拟与优化

中子反射谱仪为中国先进研究堆（ChinaAdvancedResearchReactor，CARR）中子散射工程中的一个重要的子项目，目前，该谱仪的物理概念设计已经完成。该谱仪结构复杂、造价昂贵、建造周期长，为了检验该谱仪各种设计参数的合理性和可靠性，保证谱仪建设顺利完成并达到预期性能，按国际惯例，利用蒙特卡罗方法对该谱仪关键部件的设计参数进行模拟与优化是十分必要的。     

反康普顿γ谱仪性能的蒙特·卡罗方法模拟

在建立反康普顿γ谱仪的过程中，用蒙特·卡罗方法对谱仪的主要性能进行了模拟计算，从而证明谱仪的物理设计是成功的。     

中国实验快堆C31系统HPGe γ谱仪效率刻度的点源模拟

中国实验快堆燃料破损覆盖气体监测系统γ谱仪采用的是ORTEC公司的HPGe γ谱仪,监测对象是覆盖气体(氩气)。由于很难找到谱仪效率刻度相对应的标准气体体源,对谱仪的效率刻度带来了困难。本文在参考大量文献的基础上利用点源模拟的方法来进行HPGe γ谱仪的全能峰效率刻度,解决了中国实验快堆燃料破损覆盖气体监测系统(C31系统)谱仪效率刻度的困难。     

能量和角度多道的环形电子能谱仪的性能研究

对以探测极角为90°、方位角收集范围为245°的环形电子能量分析器(TEEA)为基础的电子能谱仪的性能进行了研究,通过实验系统地研究了各电子光学单元的电位对谱仪能量分辨、能量线性以及线性能窗宽度的影响.同时对谱仪的能量分辨进行了深人的讨论,着重分析了仪器的角度非轴对称性对能量分辨的影响,并提出了对它的修正方法.这些对谱仪的进一步发展及将谱仪运用到固体表面能谱学和微区原子识别的研究中都有一定的意义.     

两套HPGeγ谱仪对土壤样品的测量结果比对分析

以比对的手法介绍了两套高纯锗γ谱仪的性能。采用相对测量法．分别用两套谱仪对三个土壤样品进行测量,并进行了自吸收校正,对测量结果进行了分析讨论。     

基于G(E)函数法的NaIγ谱仪能谱-剂量转换研究

利用Geant4求解国控大气辐射环境自动监测站NaI γ谱仪G(E)函数,对NaI γ谱仪进行能量响应修正,实现NaI γ谱仪能谱-剂量直接转换。通过点源刻度实验,获取NaI γ谱仪Geant4物理模型。然后利用Geant4和高斯展宽获取NaI γ谱仪对不同能量γ射线的响应能谱。最后采用最小二乘法求解得到NaI γ谱仪G(E)函数。并通过标准源¹³⁷Cs、⁶⁰Co、²⁴¹Am的实验能谱进行验证,表明利用G(E)函数和谱仪实际能量谱求空气吸收剂量率的方法是可行的。     

利用BF_3多柱谱仪测量临界装置中子能谱

研发了一种中子能谱测量装置——BF_3多柱谱仪。对BF_3多柱谱仪的工作原理、结构与性能,以及该探测系统的使用方法进行研究,并分析其可满足的实验要求。应用BF_3多柱谱仪在临界装置上进行了中子能谱测量的实验,将实验测量结果与MCNP程序的理论计算结果进行了比较,两者符合较好,验证了该中子探测系统的性能。该BF_3多柱谱仪可适用于低中子通量密度能谱测量、屏蔽实验、环境监督测量、实验大厅内部及周围环境中子场测量等多种工况。     

嫦娥一号卫星X射线谱仪能量响应矩阵的计算

介绍了嫦娥一号卫星X射线谱仪能量响应矩阵的计算方法,根据谱仪标定试验的标定数据计算了谱仪各路探测器的能量响应矩阵;根据谱仪的能量响应矩阵由直接解调方法对试验测得的放射源能谱和元素荧光能谱进行了解谱,较好的重现了放射源和各元素的特征能量.     

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.     

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。     

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.