P型同轴HPGe探测器的进展

在原有工作的基础上,我们又研制了高分辨探测器3~#和4~#,其体积分别为30 cm~3和88 cm~3,对~(60)Co的1.33 MeV之γ射线的能量分辨率分别为1.81 keV和2.29 keV。本文介绍在研制高分辨P型高纯锗同轴探测器中所取得的新进展。     

N型HPGe同轴探测器的研制

本文介绍N型高纯锗同轴探测器的特点、制备方法及其性能。我们研制成的N型同轴探测器的体积为88cm~3,相对效率约为19％,它对_(60)Co 1.33MeV γ射线的能量分辨率为2.60keV,峰康比为34。     

同轴型HPGe探测器研究成功

采用比利时Hoboken公司生产的HPGe单晶,我们研究成功了第一套同轴型HPGe探测器。经初步测试,其主要性能如下:探测器为双开端同轴;灵敏体积34cm~3(单晶?42mm×25mm,孔心直径8mm。);在1050伏偏压下,对1.33 MeVγ射线,能量分辨率为2.30 keV,脉冲产生器宽度为1.39 keV,     

n型同轴高纯锗探测器

本文介绍了研制n型同轴高纯锗探测器的方法及技术。探测器具有薄的(约0.3μm)离子注入p~+外接触,可探测0.005—10MeV的X和γ射线,并具有较高的耐辐射损伤性能,所研制成的探测器灵敏体积约120cm~3,对1.33MeVγ射线:相对效率为24.5％,能量分辨率为2.13keV,峰康比为48.3:1,电子学噪声为1.28keV。     

大灵敏体积平面型HPGe探测器

本文介绍采用P型HPGe单晶研制大灵敏体积平面型HPGe探测器的结果。最大灵敏体积为15cm~3,对59.6keV和1.33MeVγ射线的分辨率各为1.26keV和2.07keV。     

极大体积(>200cm~3)同轴HPGe探测器的研制及其特性

文章叙述了极大体积(～220cm~3)同轴HPGe探测器的研制及其性能。分析了各种因素对探测器系统分辨率的影响。探测器对~(60)Co的1.33MeVγ射线,能量分辨率FWHM=2.30±0.02keV,相对效率η=44.56%,峰对称性FW(1/10M)/FWHM=1.90;对2.60MeVγ射线,FWHM=3.10 keV。     

CdTe核辐射探测器(扩散型)

CdTe核辐射探测器是近年来发展起来的有希望的一种化合物半导体探测器。目前,采用CdTe材料已制成扩散型、面垒型、离子注入型、同轴型等探测器。而扩散型探测器是早期开展的工作,1971年А.И.Калучина等人制成了扩散型CdTe探测器,对~(241)Am 59 keV的γ射线获得7 keV的能量分辨率(FWHM)。     

Ge(Li)探测器表面现象的研究

对同轴Ge(Li)探测器进行不同表面处理,采用~(241)Am59.6 keV准直γ束扫描来研究探测器的表面性能。从测得的探测器表面各点脉冲谱及光电峰相对效率,说明在探测器表面存在着强弱不同的N或P型表面沟道。当探测器表面存在N型沟道时,可得到比较好的探测器特性。     

同轴HPGe探测器的全能峰效率测量及效率曲线斜率的经验公式

采用~(60)Co和~(152)Eu放射源,测定了灵敏体积为31.6,118.0和221.0cm~8的同轴HPGe探测器的全能峰绝对效率与121.8—1408keV能区内γ射线的能量关系,并用最小二乘法对效率曲线进行了较好的拟合。在极大的灵敏体积范围内,验证了锗探测器效率曲线斜率与其灵敏体积关系的经验公式:S=alogV+b,采用本公式可在小于3％的相对误差范围内,对已知灵敏体积的同轴HPGe探测器的全能峰效率随γ射线能量的变化作出估价。     

超纯P型硅探测器的制备和室温特性

本文主要叙述超纯P型硅探测器的制备和性能。应用浙江大学研制的超纯硅单晶制成50mm~2×1.5mm的Si(Hp)探测器,在室温10℃,对~(270)Bi 481.6keV和976keV内转换电子的能量分辨率分别为6.3keV和8.58keV;对~(137)Cs624keV内转换电子能量分辨率为7.1keV。     

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.