固相萃取片法分析土壤中的~(99)Tc

系统研究了阴离子固相萃取片分离水溶液中TcO-4的性能,包括流速、酸度、体积、土壤基质对吸附的影响。在此基础上,针对土壤中99 Tc含量的分析,建立了以固相萃取片法为主要分离手段、液闪为放射性测量方法的分析流程,并利用模拟99 Tc污染土壤样品对分析流程进行了检验。研究结果表明,土壤中含有的本底放射性核素及常见沾污核素137 Cs、90 Sr-90 Y和天然铀对分析流程均无明显干扰,全流程99 Tc的化学收率在95%以上。样品质量为10g、液闪测量能量范围本底计数率为10min-1、测量时间为10h时,方法的最小可探测浓度约为0.07min-1·g-1,即1.1Bq/kg。     

固相萃取片法分析土壤样品中的~(239)Pu

为了对核设施及周边环境的放射性污染水平进行有效监测,需要对土壤样品中的~(239)Pu进行分析。本研究考察了静态吸附中介质酸度、接触时间以及温度对~(239)Pu在固相萃取片上的吸附影响,确定最佳吸附条件;采用柱实验进行验证,以固相萃取片法为分离纯化手段,采用高酸上柱,低酸条件下还原解吸,以低本底液闪谱仪为放射性测量手段,建立快速分析土壤中~(239)Pu的方法。该方法可测土壤样品量为10g,使用8mol/L HNO_3浸取灰化后的模拟污染土壤样品,模拟土壤样品中~(239)Pu的化学回收率为78.9%,比活度探测下限为3.7 Bq/kg,全流程分析时间小于3h,对核素~(137)Cs、~(90)Sr-~(90)Y、天然铀、~(241)Am、~(99)Tc去污效果良好,该方法可广泛应用于环境土壤样品的~(239)Pu分析。     

ICP-MS测定低放废水中的~(99)Tc

针对中国原子能科学研究院的低放废水处理过程中99Tc的分析 ,研究建立了甲乙酮萃取 /ICP MS测量99Tc的方法。应用建立的方法首次测量了低放废水处理过程中原水、絮凝水、排放水中99Tc的含量 ,并计算出絮凝工段、蒸发工段对99Tc的净化系数。作为比较 ,还用反康普顿Ge(Li)γ谱仪测量了其它放射性核素和用切连科夫液闪直接计数法测量了90 Sr 90 Y的含量     

ICP—MS测定低放废水中的^99Tc

针对中国原子能科学研究院的低放废水处理过程中^99Tc的分析，研究建立了甲乙酮萃取／ICP－MS测量^99Tc的方法。应用建立的方法首次测量了低放废水处理过程中原水、絮凝水、排放水中^99Tc的含量，并计算出絮凝工段、蒸发工段对^99Tc的净化系数。作为比较，还用反康普顿Ge(Li)γ谱仪测量了其它放射性核素和用切连科夫液闪直接计数法测量了^90Sr-^90Y的含量。     

2,6-二甲基吡啶萃取-液闪法测定后处理厂中的~(99)Tc

研究了2,6-二甲基吡啶萃取分离-液体闪烁法测定后处理厂工艺料液中99 Tc的分析方法。进行了铀、镎、钚、裂片元素对99 Tc测定的干扰与消除实验,对分离条件、液闪测量条件进行了优化。在选定条件下对模拟样品进行分析,精密度(sr)优于5%(n=6),99 Tc回收率为95%~105%。     

DGA树脂萃取色层法分析土壤样品中的~(241)Am

为了对核设施及周边环境的放射性污染水平进行有效监测,需要对大量土壤样品中的~(241)Am进行分析。本工作首先考察了接触时间、介质酸度、温度对~(241)Am在DGA树脂柱上的吸附影响,确定了最佳吸附条件,为动态柱实验提供了输入条件;然后进行了动态柱实验的验证:以萃取色层法为分离纯化手段,采用高酸上柱,EDTA络合解吸,以低本底液闪谱仪为放射性测量手段,建立了一个快速分析土壤中~(241)Am的方法。当土壤样品量为10g,使用8mol/L HNO_3浸取灰化后的模拟污染土壤样品,该方法对~(241)Am的化学回收率约为95%,最低可探测比活度为3.1Bq/kg,全流程分析时间小于3h。对其它核素~(137)Cs、~(90)Sr-~(90)Y、~(239)Pu、~(99)Tc有很好地去污能力。因此该方法可广泛应用于环境土壤样品的~(241)Am分析。     

PUREX流程还原性介质中99 Tc的测量

提出了一种从PUREX流程还原性介质（以1BP料液为例）中分析测量⁹⁹Tc的方法，分析过程包括钚的萃取分离、锝的氧化、定量萃取及液闪法测量。首先将样品中钚调为+4价，用1-苯基-3-甲基-4-苯甲酰基吡唑酮-5（PMBP）将钚快速萃取分离；然后用重铬酸钾在50 ℃条件下将锝氧化为+7价，并将样品调为碱性后，用2，4，6-三甲基吡啶在碱性介质中定量萃取，用液闪法进行有机相中Tc浓度的测量。采用该方法，可在20 min内完成PUREX流程还原介质中锝的分析，相对标准偏差为0.6%（n=3）。     

PUREX流程还原性介质中99Tc的测量

提出了一种从PUREX流程还原性介质（以1BP料液为例）中分析测量⁹⁹Tc的方法，分析过程包括钚的萃取分离、锝的氧化、定量萃取及液闪法测量。首先将样品中钚调为+4价，用1-苯基-3-甲基-4-苯甲酰基吡唑酮-5（PMBP）将钚快速萃取分离；然后用重铬酸钾在50 ℃条件下将锝氧化为+7价，并将样品调为碱性后，用2，4，6-三甲基吡啶在碱性介质中定量萃取，用液闪法进行有机相中Tc浓度的测量。采用该方法，可在20 min内完成PUREX流程还原介质中锝的分析，相对标准偏差为0.6%（n=3）。     

从高放废液中分离79 Se的流程研究

建立了离子交换法与沉淀法相结合的、从高放废液中分离79Se的放化流程.该流程具有去污效果好的特点,对137Cs,90Sr,90Y,99Tc,154Eu的去污因子大于104,对125Sb,113Sn的去污因子大于103,对237Np为2×102.整个流程的收率约为53%.由该流程分离出的79Se样品能够很好地满足液闪测量和质谱测量的要求.     

环境土壤样品中~(99)Tc的分析方法研究进展

随着核能的开发及核医学诊断的发展,~(99)Tc的研究日益受到重视。~(99)Tc具有半衰期长、裂变产额高和迁移性强等特点,在核废物的地质处置、环境安全评价及生物效应方面倍受关注,准确测定环境土壤样品中~(99)Tc的含量显得至关重要。本文在文献调研的基础上较详细总结了Tc的化学性质,并对~(99)Tc分析流程中样品的预处理、化学分离纯化、制源及测量等过程中涉及的主要方法进行了综述,指出了现今分析方法中存在的主要瓶颈,并对环境样品中~(99)Tc的分析做了展望。     

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.