正电子湮没技术测量冷却方式对Zr在Ni3Al中扩散行为的影响

测量了在Ni3Al（Zr）合金经高温均匀化处理后,在空冷和水冷条件下的正电子寿命谱。结果表明,Ni3Al（Zr）合金经高温均匀化后,随即进行空冷时,随着Zr含量的增加,正电子在合金中的寿命谱特征参数降低,捕获率置降低。表明Zr原子扩散到晶界,并在晶界偏聚。而合金经高温均匀化后水冷时,合金的正电子寿命谱特征参数随着Zr含量的增加几乎没有变化。由于冷却速度较快,Zr原子来不及扩散到晶界上,而以固溶方式存在于Ni3Al基体中。     

Cr和Mo对Fe3Al合金中微观缺陷和电子密度的影响

测量了二元Ｆｅ３Ａｌ及含Ｃｒ或Ｍｏ的Ｆｅ３Ａｌ合金的正电子寿命谱参数,计算了合金基体和缺陷处的价电子密度。实验结果表明,Ａｌ和Ｆｅ结合形成Ｆｅ３Ａｌ合金时,Ａｌ原子提供价电子与Ｆｅ原子的３ｄ电子形成局域的共价键。Ｆｅ３Ａｌ合金中金属键和共价键共存。Ｆｅ３Ａｌ合金晶界缺陷的开空间大于Ｆｅ空位或Ａｌ空位的开空间,晶界缺陷处价电子密度比基体低,晶界的键合力较弱。在Ｆｅ３Ａｌ合金中加入Ｍｏ,降低了合金中的     

用单能慢正电子束测量Si中的正电子迁移率

用单能慢正电子束流作为探针,测量了Ｐ型Ｓｉ中不同Ｂ杂质浓度的正电子湮没Ｓ参数和正电子能量的函数关系。在实验上系统地研究了正电子扩散长度和迁移率随半导体中杂质浓度的变化规律,观察到杂质的掺入不影响缺陷的开体积,但正电子在硅中的迁移率随杂质浓度的增加而减小。     

用正电子湮没研究Al-Ni二元系的固溶体类型

Al-Ni二元系δ相理想成份为Ni_2Al_3。有文献报道,在其富Al端形成替代固溶体,而在富Ni端,Ni原子填在空缺的位置上,β相理想成份为NiAl,富Ni端形成替代式固溶体,在富Al端,形成Ni的缺位固溶体。按这样模型算出了价电子密度(D_v)和总电子密度(D_t)。计算的D_v和测得的S线型参数以及计算的D_t和测得的正电子湮没寿命τ_1分别列在图1和图2。     

D-D中子辐照单晶TiO2的损伤特性

利用兰州大学强流中子发生器出射的单能D-D中子对单晶TiO2(金红石相)进行辐照,分别测量了样品的正电子寿命谱及XRD谱。中子辐照会在样品内部产生大量的空位缺陷,由于晶格中Ti原子的位移阈能约为O原子的2倍,因此中子辐照在样品内部产生的空位缺陷以氧空位(VO)为主。结果表明,单晶内部捕获正电子的陷阱Ti空位(VTi)在中子辐照后电子密度增大,可能与Ti空位周围O空位的引入有关,O空位的出现减弱了Ti空位处的库仑排斥作用,使空位体积减少。后续测试的XRD也得到相同的结果,样品由于中子辐照而在c轴方向的晶面间距发生变化,并导致单晶TiO2的结晶度变差。     

Co-Ga二元系β相的正电子湮没的研究

Co-Ga合金β相的点阵常数随at.％Ga成份而变化,在48at.％Ga处有一最大值。在富Co端能被解释为替代式固溶体,但在富Ga端存在什么类型固溶体?本文用正电子湮没寿命和S参数来研究Co-Ga体系中β相固溶体的类型。     

Ni3Al（0.98at%B）中硼原子扩散行为的正电子湮没研究

用正电子湮没技术研究了Ｎｉ３Ａｌ（０．９８ａｔ％Ｂ）合金经高温均匀化处理后，在空冷、炉冷、水冷条件下硼原子的扩散行为，结果表明，炉冷处理的合金中扩散至晶界的硼原子最多，并有微量硼化物在晶界处析出：水冷处理时扩散至晶界的硼原子最少，为使既有较多的硼原子扩散至晶界，又无硼化物在晶界析出，宜采用高温均匀化空冷的热处理工艺。     

掺Pb超导体（Bi2—xPbx）Ca2.5Nd0.5Cu2O8＋y的正电子寿命研究

室温测量了（Ｂｉ２－ｘＰｂｘ）Ｃａ２．５Ｎｄ０．５Ｃｕ２Ｏ８＋ｙ超导体的正电子寿命与Ｐｂ含量的关系。在２２１２相发现随着Ｐｄ含量的增加正电子体寿命相应地减小，分析表明，这是由于Ｐｂ替换了Ｂｉ，使电子从Ｃｕ－Ｏ面或其它晶位迁移到Ｂｉ－Ｏ层，并导致Ｂｉ－Ｏ层电子密度增加所致。     

用正电子湮没技术研究Ni－20Al－30Fe合金中的缺陷组态

测量了铸态、热轧和定向结晶三种不同工艺的Ｎｉ－２０Ａｌ－３０Ｆｅ的ｅ＋寿命谱：ｅ＋这三种试样的缺陷中的寿命十分相近．说明ｅ＋在该合金的空位、应错和晶界中的寿命相近．合金晶界缺陷处的自由电子密度和空位处的相当。在ＮｉＡｌ合金中加入Ｆｅ元素后．改善了合金的晶界结构．     

非晶态FeCuNbSiB系合金结构缺陷的正电子湮没研究

通过测量不同温度下退火的非晶合金Ｆｅ７３．５Ｃｕ１Ｎｂ３Ｓｉ１３．５Ｂ９和Ｆｅ７３．５Ｃｕ１Ｎｂ１．５Ｍｏ１．５Ｓｉ１３．５Ｂ９的正电子湮没有寿命谱，配合Ｘ射线衍射分析，研究了非晶合金结构缺陷随退火温度的变化。结果表明，非晶合金中存在两种类型的自由体积。正电子湮没有寿命随样品退火温度的变化曲线对应着结构弛豫，局域晶化和完全晶化阶段。     

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。     

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.     

Gamma radiation levels in the ambient environment of the QNPP Base

Monitoring results of gamma dose rate level in 1992～2004 in the ambient environment of the Qinshan Nuclear Power Plants(QNPP)Base,the northeast of Zhejiang Province,are reported in this paper.It is shown that the gamma dose rate of five monitoring sites of 2.5 km to QNPP Base is 84～113 nGy/h,with an average of 96 nGy/h in the 13 years.The average value is close to the background level of 93 nGy/h prior to operation of the QNPP Base,and is lower than the monitoring result of 101 nGy/h at the reference site in Hangzhou City.Within 50 km from the QNPP Base,the cumulative dose rate of the thermoluminescent dosimeter(TLD)is 90 nGy/h,which is lower than the back- ground level of 111 nGy/h.     

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.