在硝酸铀(Ⅳ)还原反萃取钚(Ⅳ)的混合澄清槽实验中铀(Ⅳ)的稳定性研究

本文以肼作稳定剂,在中间工厂规模的混合澄清槽设备上研究了TBP萃取流程的铀钚反萃过程中硝酸铀(Ⅳ)还原剂的动态稳定性及肼的反应产物叠氮酸的最大积累浓度。实验中测得铀(Ⅳ)的稳定性高于文献报道的数据;叠氮酸的最大积累浓度远低于允许浓度,从而肯定了硝酸铀(Ⅳ)用作铀钚还原反萃过程中还原剂的可能性。     

铀酰离子光化学研究——Ⅰ.Ar~ 激光对UO_2(NO_3)_2-C_2H_5OH-HNO_3体系U(Ⅵ)的光化学还原

利用氩离子激光器的4880A激光照射UO_2(NO_3)_2-C_2H_5OH-HNO_3溶液体系,研究了乙醇浓度、硝酸浓度、铀(Ⅵ)浓度和温度对铀(Ⅳ)表观量子产额φ的影响。0.01MUO_2(NO_3)_2-1.5MC_2H_5OH-0.5MHNO_3溶液驱氧并保持在氮气氛下光照,φ最高可达0.8左右。当HNO_3浓度大于1.0M时,φ的下降与体系中形成HNO_2有关。对比了加入氨磺酸条件下的实验结果。初步讨论了可能的光化还原U(Ⅵ)-U(Ⅳ)的反应机制。     

在UO_2(NO_3)_2-TBP-CCI_4有机相中光化还原制备铀(Ⅳ)的研究

本文的目的是研究在TBP有机相中光化还原铀(Ⅵ)以制备铀(Ⅳ)。选用了高压汞灯作为激发光源,CCl_4为TBP的稀释剂。研究了反应温度、原始水相溶液组成等因素对铀(Ⅳ)产额和亚硝酸生成量的影响。推荐了制备铀(Ⅳ)的适宜条件。     

甲醛光化还原硝酸铀酰制取硝酸铀(Ⅳ)的研究

本文针对实际应用探讨了汞灯做光源、用甲醛光化还原硝酸铀酰制备硝酸铀(Ⅳ)的适宜工艺条件。提出了铀(Ⅳ)的生成速率方程式,并用试管实验和立升规模实验进行了初步验证。     

异丁醛还原Pu(Ⅳ)的动力学研究

在硝酸介质中,研究异丁醛(IBD)还原Pu(Ⅳ)反应的动力学性能和行为,通过考察Pu(Ⅳ)浓度、异丁醛和硝酸浓度等对Pu(Ⅳ)还原反应速率的影响,确定了反应的动力学速率方程。研究温度对速率的影响,求得反应活化能为51.7kJ·mol~(-1)。实验表明,异丁醛是Pu(Ⅳ)较好的还原剂。对还原反应的机理作了推测。     

硝酸铀(Ⅳ)稳定性的研究

本工作以尿素作稳定剂,对硝酸铀(Ⅳ)水溶液的稳定性作了研究。讨论了铀(Ⅳ)不稳定的原因,主要是在硝酸中存在着亚硝酸,后者可将四价铀氧化至六价。还讨论了酸度、温度、铀浓度、稳定剂浓度、光照及辐射等因素对硝酸铀(Ⅳ)稳定性的影响,从而确定了获得稳定硝酸铀(Ⅳ)溶液的条件。     

U(Ⅳ)对Pu(Ⅳ)的单级还原反萃实验和计算研究

正采用U(Ⅳ)为还原剂,研究了30%TBP/正十二烷中Pu(Ⅳ)的单级还原反萃取行为,考察了相接触时间、还原剂浓度、酸度、支持还原剂浓度对Pu(Ⅳ)反萃率的影响。单级反萃实验在玻璃离心管中进行,将有机相料液和U(Ⅳ)的还原反萃液按照1∶1相比加入离心管中,在室温下振荡器震荡至预定时间,快速离心分相,分相后分别取有机     

硫酸溶液中铀酰离子的激光光化还原

本文研究了硫酸溶液中铀酰离子的激光光化还原,选用CW He-Cd激光器的波长为4416(?),测得25℃时生成U(Ⅳ)的量子产额为0.69±0.03;研究了乙醇,硫酸和铀酰离子浓度对量子产额的影响。在[C_2H_5OH]>0.5M、[H_2SO_4]>2.0M和[UO_2~(2 )]>7.0×10~(-3)M时,它们的浓度变化对量子产额影响不大。在25℃和1.7M乙醇浓度下,测定了硫酸中氢离子和铀酰离子浓度与反应速率的关系,得到在一定条件下光化还原生成U(Ⅳ)的速率ν与[H~ ]和[U(Ⅵ)]的关系式为: v=k[H~ ]°[UO_2~(2 )]~6 由实验求得上式中常数a和b分别为0.16和1.3,计算出表观反应速率常数为4.1×10~(-5)(M,sec,mW)。     

用荧光法指示终点的滴定法测定铀

根据荧光法原理所制订的各种方法,已用于铀(Ⅵ)的分析,但荧光法原理似乎还没有应用到铀的滴定法方面来。用荧光法指示终点的铀的滴定法,也许是洲定铀的选择性的灵敏的方法。测定铀的许多滴定方法,已经提出来了。大多数滴定方法是用金属还原剂将铀(Ⅵ)还原到铀(Ⅳ),接着用氧化滴定法。几乎所有的滴定方法均局限于>10~(-3)M的浓度范围。只有一篇文章谈到了用恒电位库仑滴定法测定     

在TBP-煤油有机相中光化还原制取U(Ⅳ)的研究——Ⅱ.降解产物的产生和它们对萃取的影响

本文研究了在TBP-煤油体系中光化还原制取U(Ⅳ)时,降解产物的产生和它们对萃取性能的影响。结果表明,TBP-煤油的主要降解产物有DBP和MBP、羰基化合物和硝基烷。光照后的有机相经稀酸反萃和碱洗所得回收萃取剂的萃铀分配比、铀保留值和分相时间与新鲜萃取剂无明显差别)。     

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.