田湾核电站附近海域海水中137Cs活度浓度分析与评价

介绍了田湾核电站附近海域海水中¹³⁷Cs的监测方案以及质量保证措施,给出了电站投运后¹³⁷Cs通过气态途径与液态途径的排放量以及2004—2015年的监测结果,并将监测结果与本底调查结果及海水水质标准规定的数值进行了比较。监测结果表明,电站运行前后海水中¹³⁷Cs活度浓度与本底调查结果有明显差异;监测结果远小于海水水质标准规定的数值。     

秦山核电厂运行前的环境放射性本底调查和运行期间的环境监测计划

本文主要介绍秦山核电厂运行前的环境放射性本底调查的方法和结果，同时简要概述了运行中的环境监测计划。文中着重叙述了运行前本底调查和运行初期环境监测计划的目的，原则以及调查方案，其中包括监测范围、项目、周期、测点布设和监测用的主要仪器和方法。同时还给出了一些重要测点上的主要测量结果。     

秦山地区环境放射性本底调查报告

阐述了从1986年6月到1991年7月历时近五年的秦山核电厂运行前环境放射性本底调查工作和调查结果。着重描述了本底调查方案的设计,调查中所采用的测量分析方法和采取的质量保证措施。本底调查方案设计主要是依据国家有关法规和本地区的环境状况,其测量分析方法均采用国家标准方法。在本底调查中,质量控制贯彻在从采样—分析测量—数据处理的全过程中。参加了实验室间各种介质和核素的测量分析比对。近五年的本底调查是获取数据约5000个,为核电厂运行后的常规环境监测提供了宝贵的基础资料。     

秦山地区环境放射性本底调查报告

阐述了从1986年6月到1991年7月历时近五年的秦山核电厂运行前环境放射性本底调查工作和调查结果。着重描述了本底调查方案的设计,调查中所采用的测量分析方法和采取的质量保证措施。本底调查方案设计主要是依据国家有关法规和本地区的环境状况,其测量分析方法均采用国家标准方法。在本底调查中,质量控制贯彻在从采样-分析测量-数据处理的全过程中。参加了实验室间各种介质和核素的测量分析比对。近五年的本底调查共获取数据约5000个,为核电厂运行后的常规环境监测提供了宝贵的基础资料。     

大亚湾核电站1994～2003年环境辐射监测结果与分析

本文总结了大亚湾核电站自商业运行以来十年(1994～2003)间对其周围的环境辐射监测.介绍了监测系统、方案和方法、主要结果及其初步评价.评价表明,周围地区的辐射环境状况,除在牡蛎等少数海洋生物中测到与电站排放相关的痕量放射性核素110mAg及厂区监测井中有时测到高于本底的氚外,基本上保持在运行前的本底水平.     

大亚湾核电站1994～2003年环境辐射监测结果与分析

本文总结了大亚湾核电站自商业运行以来十年 ( 1 994～ 2 0 0 3 )间对其周围的环境辐射监测。介绍了监测系统、方案和方法、主要结果及其初步评价。评价表明 ,周围地区的辐射环境状况 ,除在牡蛎等少数海洋生物中测到与电站排放相关的痕量放射性核素110mAg及厂区监测井中有时测到高于本底的氚外 ,基本上保持在运行前的本底水平     

大亚湾核电站1994～2003年环境辐射监测结果与分析

本文总结了大亚湾核电站自商业运行以来十年(1994～2003)间对其周围的环境辐射监测。介绍了监测系统、方案和方法、主要结果及其初步评价。评价表明,周围地区的辐射环境状况,除在牡蛎等少数海洋生物中测到与电站排放相关的痕量放射性核素^110mAg及厂区监测井中有时测到高于本底的氚外,基本上保持在运行前的本底水平。     

对核电站运行前环境本底监测方案的几点看法

核电站运行前的环境放射性本底调查是核电站环境影响报告书中的重要内容之一。运行前环境本底监测的目的是:对核电站运行前的周围环境介质,包括空气、水、土壤、沉降物、动植物、海水及海生物等进行本底调查,查明环境介质中原有的放射性水平及其变化规律,为评价核电站运行之后环境介质中放射性水平的变化提供基本数据,并为改进运行阶段的环境放射性监测方案提供经验。在编制核电站运行前的环境本底监测方案时,有必要对本文提出的几个问题加以考虑,以便使编制的本底监测方案尽可能合理。     

秦山核电基地辐射环境监测20年

介绍了秦山核电基地近20年(1992—2011年)辐射环境监测概况,包括监测方案、方法及设备、质量控制措施及环境中主要放射性核素监测数据;对监测结果进行了简要分析;总结了运行期间进行环境辐射监测遇到的主要技术难点、经验和教训。监测结果表明秦山核电基地多机组的运行未对环境造成可察觉的影响,辐射环境质量与运行前基本相同。     

田湾核电厂环境辐射本底初步调查

介绍田湾核电厂环境福射本底水平调查的目的、方法以及调查方案,包括监测范围、点位布设、实验室分析仪器和质量检测措施及样品测量,同时给出调查结果。     

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.