国产改进型316L不锈钢的微结构研究

采用正电子湮没寿命方法研究了国产改进型316L不锈钢的微结构及其温度变化。该不锈钢含有单空位、双空位、位错和小空位团等缺陷。经400℃,600℃,800℃退火后,单空位、双空位和位错缺陷分别消失。小空位团是四空位和五空位构成的空位团,低于200℃退火,缺陷复合五空位团成分随退火温度升高而增大,高于400℃时空位团分裂,五空位团成分减少,800℃退火还存在较低浓度的四空位团。     

裂变快中子辐照在GaAs中产生缺陷的正电子湮没研究

采用自电子湮没寿命测量方法研究了注量为６．５×１０＾１５／ｃｍ＾２和１．４×１０＾１４／ｃｍ＾２，Ｅｎ≥１ＭｅＶ的裂变中子辐照在掺Ｓｉ，Ｎ型单晶ＧａＡｓ产物的缺陷，此辐照在ＧａＡｓ中产生单空位和双空位缺限，缺陷浓度于比于辐照注量，高温退火产生三空位缺陷及小空位团，单空位，双空位和三空位缺陷的退火温度分别为２５０，４５０，６５０℃。     

中子辐照注量对单晶硅中缺陷退火行为的影响

用正电子湮没寿命和多普勒加宽测量研究了不同注量中子辐照的氩气氛区熔单晶硅中缺陷的退火行为，发现不同中子注量辐照时，辐照致空位型缺陷的退火行为十分类似，并均在５５０℃时退火消除；但辐照致双空位浓度、二次双空位和四空位型缺陷的产生、浓度和消除温度很不相同。简单陷阱模型不适用于５００℃以下退火的离中子注量辐照的单晶硅，但能部分适用于中等注量辐照的单晶硅。     

慢正电子束研究质子辐照CLAM钢产生的缺陷及其退火行为

为了研究中国低活化马氏体CLAM钢的辐照损伤机理,本文利用慢正电子技术研究了质子辐照CLAM钢时所产生的缺陷及其退火回复行为,发现辐照在材料中产生空位团数密度随质子注量增加而增多,而其尺度增大并不明显.辐照仅产生原子尺度的空位和空位团,400℃退火可以使缺陷很好地消除.此外分析了硅对CLAM钢辐照性能的影响,实验上没有观察到硅的添加抑制了质子辐照缺陷的产生.     

新型U3Si2-Al燃料板的正电子湮没寿命谱研究

用正电子湮没寿命谱仪对U3Si2-Al燃料板样品的正电子湮没寿命进行了测量及分析,得到不同工艺状况下燃料包壳材料微观缺陷的形态及变化趋势.回火态燃料板包壳基体中的微观缺陷以单空位的点缺陷为主;冷作态中的缺陷以双空位、位错等缺陷为主;冲刷态中的缺陷以层错、小的空位团等缺陷为主.3种样品中,均未发现影响燃料板安全的大空位团缺陷.回火和冲刷等工艺或运行工况,会使燃料板包壳基体中的微观缺陷发生转变,并改变了燃料板的宏观力学性能.     

TiAl金属间化合物的淬火缺陷研究

采用自电子寿命谱技术研究了ＴｉＡｌ以下Ｔｉ３Ａｌ金属间化合物的淬火缺陷及其回复行为，结果表明，充分退火ＴｉＡｌ试样中有一定数量的晶界存在的ＴｉＡｌ合金高温淬火过程中在产生大量空位的同时也产生了一定数量的空位团和空位－杂质原子复合体等二次缺陷，在３００－６００℃的温度范围内，由于这些复合缺陷的分解和迁移，使空位团进一步聚集长大。     

充氚不锈钢中氦行为的PAL和TEM研究

对充氚和未充氚的抗氢-2(HR-2)不锈钢样品进行退火处理,利用正电子湮没寿命谱(PAL)以及透射电镜(TEM)等技术探讨不锈钢中氦和微缺陷的相互作用。未充氚样品中,退火温度对缺陷态的影响主要表现为偏聚物在晶界的析出。充氚样品实验中,退火温度小于300℃时,充氚不锈钢中的He原子主要通过自捕获机制在晶内缺陷处聚集成泡;热处理温度为300～600℃时,充氚不锈钢中的He原子主要通过热迁移的方式迁移至晶界导致晶界宽化,但晶界处无明显的He泡形成;热处理温度大于600℃时,热平衡空位开始发挥作用,与聚集在晶内缺陷处的He原子结合形成He泡,且随退火温度的升高,He泡有明显聚合长大的现象。     

BCC金属Nb的重离子辐射损伤研究

采用81 MeV碳离子辐照,模拟中子注量为10~(23)/cm~2的堆中子在Nb中产生的辐射损伤,用时间微分扰动角关联和正电子湮没二种方法研究辐射损伤及其高温退火效应。实验发现经注量2.5×10~(16)/cm~2的碳离子辐照后,在BCC金属Nb中产生单空位和双空位二种缺陷。随退火温度升高,双空位分解,单空位的总浓度逐步减小,经过1058K退火后,在Nb中由辐射损伤造成的缺陷消失。     

中子辐照硅的正电子湮没研究

采用正电子湮没方法研究了１．４５×１０＾２０ｎ／ｃｍ＾２和３．１０×１０＾１７ｎ／ｃｍ＾２快中子辐照高纯单晶硅的辐射损伤及其退火效应。在３４３－１０７３Ｋ温度范围内测量了正电子湮没寿命随退火温度的变化。实验观察到氧－空位对和在高中子剂量辐照的Ｓｉ中发现的双空位复合成四空位。正电子湮没短寿命成分τ１是晶格正电子寿命和氧－空位对捕获的正电子寿命的加权平均值，而长寿命成分τ２是双空位或四空位捕获的正电子     

中子辐照GaAs的变温正电子寿命研究

用正电子湮没寿命谱研究中子辐照前后半绝缘ＧａＡｓ在等时退火过程中的缺陷行为．发现辐照后的样品大约从７０℃起空位－填隙子对和空位－反格点缺陷开始复合．５００℃前空位和空位团可消除．７４０℃后可能会重新产生缺陷。ＶＡｓ是一种浅势阱，对正电子的束缚能大约为０．０３１－０．０３２ｅＶ。     

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.     

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.     

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.