克量级铀中微量铕和铽的放化分离方法研究

为提高中子诱发铀裂变时低产额裂变产物~(156)Eu和~(161)Tb产额测量的精度,需获得放化纯的~(156)Eu和~(161)Tb样品。本工作建立了氢氧化物共沉淀法除铝、氟化钙共沉淀法除铀、TRPO萃取法提取稀土元素、阳离子交换色谱法从混合稀土元素中分离Eu和Tb的流程,可用于大量铀、铝和裂变产物中微量Eu和Tb的分离。在待分离样品中含2 g铀、0.65 g铝和裂变产物的条件下,该流程对Eu、Tb的化学回收率均大于80%,对U、~(239)Np、~(95)Zr、~(103)Ru、~(131)I、~(132)Te、~(140)Ba、~(140)La、~(141)Ce、~(147)Nd等主要干扰物质的去污因子达到10~6。该方法可满足中子诱发铀裂变时~(156)Eu和~(161)Tb产额精确测量的要求。     

萃取色层法测定UF_6中裂变产物总β和总γ放射性

文章研究了在含F~-和NO_3~-的溶液中,~(95)Zr,~(95)Nb,~(106)Ru,~(144)Ce,~(234)Th和U在CL-TBP柱上的淋洗行为。选择了~(95)Zr,~(95)Nb,~(106)Ru及~(144)Ce等主要裂变产物与~(234)Th及U分离的条件。建立了对UF_6样品中裂变产物的总β和总γ放射性的测定方法。对于总β放射性为天然铀β放射性7.8%的样品,标准偏差为±3.5%;对总γ放射性为天然铀γ放时性17%的样品,标准偏差为±3.1%。     

二氧化锡吸附法分离~(95)Zr和~(95)Nb的研究

随着科学技术及同位素应用的发展,对纯~(95)Zr和~(95)Nb指示剂的需求越来越迫切。从裂变产物~(95)Zr-~(95)Nb平衡体系中分离~(95)Zr和~(95)Nb的方法很多,其中吸附法具有吸附剂来源方便、操作简单、产物纯净等优点而受到人们的重视。特别是硅胶吸附法分离~(95)Zr和~(95)Zb更是不少研究工作者的课题,但是这方面的基础研究工作如关于~(95)Nb的行为和     

用硅胶吸附提取及分离~(95)Zr和~(95)Nb指示剂

本文叙述硅胶-硝酸体系中~(95)Zr、~(95)Nb的吸附,硝酸浓度、温度、硅胶的处理、铀含量等因素对吸附的影响。提出了~(95)Zr、~(95)Nb彼此分离和从混合裂片中直接提取~(95)Zr、~(95)Nb的程序。得到的~(95)Zr中含~(95)Nb<0.4%,~(95)Nb中含~(95)Zr<0.1%。对~(106)Ru、~(187)Cs、~(144)Ce等裂变产物的去污系数大于3×10~4。     

用PMBP萃取分离测定水中示踪量~(95)Zr

裂变产物中~(95)Zr的裂变产额高,γ辐射能量高,通常列为核燃料后处理厂外环境水样和辐射卫生防护工作中的重要监测对象。 ~(95)Zr的放化分析有氟锆酸钡法;杏仁酸或其衍生物沉淀法;以及先经共沉淀剂浓集,再经萃取分离~(95)Zr等方法,氟锆酸钡法需要使用氢氟酸,操作不便。杏仁酸锆沉淀     

单能中子诱发~(235)U和~(238)U裂变的产物产额

本文利用碎片质量分布5-Gauss半经验公式,计算了单能中子诱发~(235)U和~(238)U裂变放中子前碎片产额,并采用七点拟合公式和线性内插方法求得碎片发射的中子产额。然后按照Terrell给出的转换方法,把放中子前碎片的产额换算为放中子后产物的产额。具体计算了_(40)~(95)Zr、_(58)~(144)Ce、_(60)~(147)Nb三种产物产额随入射中子能量的变化关系,并与实验观测结果作了比较。     

裂变产物中锆-95的亚化学计量测定法

本文介绍一种新的放化测定裂变产物中~(95)Zr的方法,即用亚化学计量的1-苯基-3-甲基-4-苯甲酰基吡唑酮-5(PMBP)萃取分离~(95)Zr并测量其放射性,此法避免了化学回收率的测定,简捷易行。测定结果的相对标准偏差为±1.6％。     

P204树脂和阳离子交换树脂分离Sc与裂变产物

P204对Sc有很好的分离选择性和分离能力，但由于反萃困难限制了其在Sc纯化中的应用。本工作研究了从裂变产物中分离纯化Sc的方法，建立流程如下：首先利用P204树脂对Sc的强萃取能力，将Sc与大量裂变产物分离，再通过灰化方法破坏树脂官能团，解决了吸附在P204树脂上的Sc难以解吸的问题，最后通过阳离子交换树脂实现Sc与残留Zr和Mo的分离，从而实现了Sc与裂变产物的分离。该方法对样品体积和酸度要求低，流程步骤操作简单。通过对模拟样品进行分析，Sc的回收率大于65%，对主要裂变产物的去污因子大于10³，适用于Sc与裂变产物的分离。     

裂变产额法刻度浸于铀溶液中SSTD的效率因子

本文建立了裂变产额法用以刻度浸于铀溶液中的固体径迹探测器记录裂变碎片的效率因子.这个方法基于测量一些裂变产物核素的强度,并应用文献中准确已知的裂变产额值计算出铀溶液中发生的裂变数。测量的裂变产物为~(91)Sr,~(92)Sr,~(99)Mo.~(13)Te,~(130)Ba。~(140)Ba 6种核素,实验测定了聚碳酸酯记录裂变碎片的效率因子K_(wet)为(8.52±0.0j)×(10~-)_cm。这个值和应用?Cf自发裂变刻度的结果很好地符合.     

强放射性溶液中微量铀的活化分析

本文是用比较法测定强放射性溶液中的微量铀,因常规的活化分析法不能消除样品中原存裂变产物的干扰,我们选择了~(92)Sr的子体~(92)Y作为测定核素。本法对其它裂变产物的去污系数除~(144)Ce-~(144)Pr为1×10~4外,其余都大于1×10~5。精密度为±7%。若有~(239)Pu存在时,会引起正误差。分析4～6个样品,全部分离操作时间需10个小时。     

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。     

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.     

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.     

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.     

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.     

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.