用X射线光电子能谱研究CO_2在金属铀表面的初期氧化行为

采用X射线光电子能谱技术(XPS)原位研究CO_2气体与清洁金属铀表面的相互作用机理。贫化铀试样在XPS分析真空室中经氩离子枪溅射蚀刻得到清洁金属铀表面。分别观测U4f_(7/2),Ols和Cls光电子峰随CO_2气体暴露剂量的变化,分析表面各元素化学状态的变化和表面化学反应过程。实验表明,CO_2气体首先在清洁金属铀表面解离吸附形成碳粒子、氧粒子和碳氧粒子等。吸附解离的产物导致金属铀表面形成UO_2,UC和自由碳粒子并可能生成碳酸铀。讨论了CO_2气体与清洁金属铀表面的相互作用机理,并与以前研究的O_2和CO气体与清洁金属铀表面反应的现象与机理进行了比较。     

金属轴与H2表面化学行为的XPS研究

采用X射线光电子能谱(XPS)分析研究了金属铀的清洁表面在100和200℃时与H2作用的表面化学行为。通入12.0Pa     

金属铀环境腐蚀的表面状态研究

采用显微激光拉曼和傅立叶变换红外光谱技术,结合扫描开尔文力显微镜,在线研究了金属铀在大气环境中、一定温度范围内样品表面腐蚀的微区形貌和反应产物的变化情况。结果表明,金属铀在室温时表面微区形貌呈球形凸凹粒状不均匀分布,且在颗粒边缘和凹坑处表面电位较高,易发生点蚀。在大气环境条件下会吸附空气中的O2、H2O和CO2反应生成UO2、铀酰化物和碳酸盐等,不同温度加热,铀表面首先出现活性腐蚀亮斑,并逐渐积累长大,其主要氧化产物UO2在260℃以上开始转化为U3O8。     

铀铌合金表面热氧化膜结构研究

采用X射线光电谱分析技术、结合Ar离子枪溅射,研究了大气环境、不同温度(室温、100、200和300℃)条件下铀铌合金样品表面氧化膜结构的变化情况。实验结果表明:随温度升高,氧化膜厚度增大,氧化膜结构发生明显变化。不同温度热氧化处理后,铀铌合金初始表面Nb主要以Nb2O5形式存在,在Nb2O5与金属Nb之间,总存在一定厚度的NbO及少量其他价态氧化物NbOx(0x1,1x2)的混合层。室温～200℃热氧化合金样品表面铀均以含间隙氧的UO2+x(P型)存在,其U4f7/2结合能较UO2低约0.7eV。室温条件下,氧化膜成分主要为UO2;100、200℃热氧化后,氧化膜中除UO2外,还含有少量P型UO2+x,其U4f5/2卫星峰的结合能为396.6eV。300℃热氧化后的合金样品表面为铀的高价氧化物(U3O8或UOx,2x3),U4f特征峰的结合能分别为381.8和392.2eV;氧化层为UO2和金属铀的混合物。热氧化过程中,温度对铀氧化的影响较对Nb的明显得多。     

金属铀表面氧化动力学的X射线衍射研究

利用X射线衍射和Rietveld方法研究室温～150℃和300℃下金属铀表面氧化，对氧化过程中试样的表面结构以及氧化动力学进行分析。将试样表面氧化物随时间的变化作定量计算，绘制出不同温度下金属铀表面的氧化动力学曲线，对50～150℃范围内的氧化动力学数据进行拟合，获得不同温度下的氧化反应速率常数，由此得到大气环境下金属铀表面形成UO₂的活化能为46.0kJ/mol。在300℃下，氧化产物U₃O₈逐渐在UO₂上形成，其形成过程符合成核生长机理。     

金属铀在氢氧化钠溶液中阳极氧化膜的XPS特性研究

采用X射线光电子能谱法（XPS）研究了金属铀在0．8mol/L NaOH溶液中阳极氧化膜的组成。结果表明，在本实验条件下，金属铀表面的阳极氧化膜主要由UO3和少量UO2 x组成；在超真空条件下，氧化膜中的部分 UO3逐渐还原成UO2 x。     

采用椭偏光谱技术研究铀氧化动力学

采用椭偏技术研究了45～95 ℃和5 kPa纯氧气氛中金属铀的氧化,通过不同温度下金属铀表面氧化层厚度随时间的变化规律,得到贫铀在初始氧化阶段的表面氧化层厚度与时间的关系均呈现抛物线规律;绘制出了在不同温度下金属铀表面的氧化动力学曲线,由此得到在低于100 ℃, 5 kPa的纯氧气氛下贫铀表面形成氧化物的反应活化能为87.165 kJ/mol.     

热压烧结UN陶瓷芯块的性能

UN燃料具有铀密度高、熔点高、热导率高、热膨胀系数低、辐照稳定性好等优点,是未来空间核电源、核火箭、快堆和ADS的重要候选燃料。本文采用金属铀粉与氮气在300～400℃直接发生化合反应,制得单相U₂N₃粉末。粒度为38.3 μm的U₂N₃粉末在1 600 ℃真空热压烧结,制得相对密度为93.5%、存在少量金属铀相的UN陶瓷;而18.1 μm的U₂N₃粉末在1 550 ℃真空热压烧结,制得相对密度为96.1%、不残留金属铀相的UN陶瓷,U与N的总质量分数为99.57%,每个金属杂质含量均低于50 μg/g,氧含量为1 048 μg/g,碳含量为502 μg/g。U₂N₃在1 027 ℃以上将会完全分解成UN,UN在1 627 ℃以上也会发生分解。     

一氧化碳对金属铀表层及氧化物的影响

用X射线光电子能谱(XPS)分析研究了金属铀表层和八氧化三铀的表面结构以及一氧化碳对其表面结构的影响。在一氧化碳气氛中金属铀表层氧化物和八氧化三铀中氧含量减少,O/U比值分别下降了7.2％和8.0％。研究结果表明,一氧化碳气氛可抑制金属铀表     

一氧化碳对金属铀表层及氧化物的影响

用X射线光电子能谱(XPS)分析研究了金属铀表层和八氧化三铀的表面结构以及一氧化碳对其表面结构的影响。在一氧化碳气氛中金属铀表层氧化物和八氧化三铀中氧含量减少,O/U比值分别下降了7.2％和8.0％。研究结果表明,一氧化碳气氛可抑制金属铀表面及其氧化物的进一步氧化。     

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。     

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.     

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.     

有效探测面积大于1000 cm2的正比计数器测量系统性能测试

为对自制的活性面积高达1 000 cm²的大面积源进行表面发射率定值,同时作为现有2πα、2πβ表面发射率标准装置能力的扩充,研制了一套内置式大面积2π多丝正比计数器测量系统,并利用活性区直径为8 mm的²⁴¹Am点源及活性区面积为10 cm×15 cm的大面积²⁴¹Am和⁹⁰Sr-⁹⁰Y源对其进行计量学性能测试。结果表明：计数器内计数响应均匀性优于±0.4%,有效探测面积达1 400 cm²;所得²⁴¹Am源高压坪曲线的坪长为1 400 V,坪斜为0.27%/100 V,坪区内计数变化为0.87%;⁹⁰Sr-⁹⁰Y源高压坪曲线的坪长为300 V,坪斜为0.75%/100 V,坪区内计数变化为0.80%;10次测量重复性好于0.4%,8 h内短期稳定性好于0.3%,1 a内长期稳定性好于0.8%。     

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.     

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.     

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.