CdZnTe核辐射探测器的制备

本文简要介绍了采用国产碲锌镉(CdZnTe)单晶材料制备的CdznTe核辐射探测器工艺及测试结果.对α带电粒子Thc-c/(6.04MeV、8.78MeV)FWHM=2.O%、241 Am(5.486MeV)FWHM=2.3%,137Cs低能7(662keV)FWHM=9.7%和207Bi(1048.1keV、975.6keV)内转换电子所测定的能谱.     

硅PIN光敏二极管探测X、γ射线的性能及应用

介绍了硅PIN光敏二极管和电荷灵敏前放组成的X射线探测器和配合CsI(Tl)晶体构成的γ射线探测器的性能和测量结果,同时研究了光敏二极管探测器能量分辨率的温度特性。测量X射线时,在-10℃下对241Am的59.5keV射线的能量分辨率为4.8%;用PIN光敏二极管配合10mm×10mm×10mm的CsI(Tl)晶体测量γ射线时,在20℃下对137Cs0.662MeVγ射线的能量分辨率为9.9%,60Co的1.332MeVγ射线的能量分辨率为6.4%,-10℃下的能量分辨率分别为8.7%和6.3%。     

~6LiF夹心半导体中子探测器

本文叙述了有效直径为8mm的金硅面垒探测器与~6LiF组合成的夹心半导体中子探测器。每一个面垒探测器对~(241)Am的5.486MeVα粒子的分辨率FWHM好于50keV。在热堆和快堆上测量的热中子能量分辨率为:对180μg/cm~2的~6LiF,FWHM为310keV;对30μg/cm~2的~6LiF,FWHM为70keV。为快堆中子能谱和通量测量提供了一个途径。     

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。     

N型碲锌镉探测器的制备和性能

碲锌镉(CZT)晶体由于原子序数高、禁带宽、密度大,制成低能γ射线和X射线探测器不需液氮冷却就能得到相当好的能量分辨率,且有相当高的探测效率,因此近年来发展迅速。我们实验室已制成φ8mm×1.7mm灵敏体积的CZT探测器,室温22℃下对241Am放射源59.54keV能量的γ射线能量分辨率可以达到2.06keV(FWHM)(未使用准直器),连续测量没有极化效应,并且具有很好的长期稳定性。     

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)。     

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。     

半球型CdZnTe核辐射探测器的制备与性能

CdZnTe半导体核辐射探测器具有较高的探测效率和较好的能量分辨率,可方便地应用于X、γ射线的探测,在环境监测、工业无损检测等领域具有很好的应用前景.CdZnTe探测器有多种电极结构,其中半球型结构在国内鲜有研究.该工作制备了体积为8 mm×8 m×4mm的半球型CdZnTe探测器,经测试,在室温条件下,其漏电流为nA级,对未经准直的241Am(59.5 keV)、57Co(122 keV)、137Cs( 662keV)γ射线的分辨率(FWHM)分别为6.96％、5.66％、3.92％,在连续使用的条件下具有较好的稳定性.     

一个同轴Ge(Li)探测器的快中子辐射损伤

实验结果表明:本文给出的探测器对快中子辐射损伤的灵敏度相当高。当累积中子通量为6.22×10~8cm~(-2)时,探测器对~(60)Co 1.33MeV γ射线的能量分辨(FWHM)大幅度变坏,为辐射损伤前的三倍;观察到了损伤后的能量分辨的瞬态变化现象;用~(137)C662keV的γ射线扫描技术从实验上再次证明了快中子辐射在探测器中产生空穴陷阱,导致能量分辨变坏。采用简单的净化漂移方法,能恢复损伤过的探测器的性能。     

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。     

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.