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。     

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。     

MCNP模拟HP-Ge探测器效率刻度曲线

利用MCNP模拟得到了某型HP-Ge探测器对一系列不同能量γ射线的响应能谱,根据响应能谱得到了相应的全能峰探测效率,在此基础上对探测器效率刻度曲线进行了模拟,可为HP-Ge探测器的设计和使用提供参考和依据。模拟结果表明:探测器对低能γ射线(60~300 keV)探测效率较高,随着能量的增加其效率逐渐减小;对能量在160 keV~1.8 MeV范围的γ射线,探测器效率与射线能量在双对数坐标中的关系为一条直线。     

P型同轴HPGe探测器

本文介绍了P型同轴HPGe探测器的制作方法及其性能,并给出了P型同轴HPCe探测器表面效应的初步结果。研制成的同轴探测器的耗尽体积为34cm~3和98cm~3,对1.33MeVγ射线,能量分辨率分别为2.15keV和2.65keV,相对效率分别为6和19.5％。     

ICI探测器单位γ灵敏度研究

探测器灵敏度及其能量响应特性在探测器的设计和研制过程中占有十分重要的地位.从理论和实验两个方面研究了ICI探测器的γ灵敏度及其γ射线能量响应特性.在60 Co 1.25MeV γ辐射源装置上进行实验测量得到ICI探测器的单位γ灵敏度为1.8×10-20 (±5%)C·cm2 ,理论计算的单位γ灵敏度为1.78×10-20 C·cm2 (γ能量1.25MeV),理论和实验结果符合得较好.研究结果表明,入射γ射线能量在1～10MeV范围内变化时,ICI探测器具有平坦的γ灵敏度响应曲线.     

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,     

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%。     

NTD硅探测器

采用国产NTD硅单晶,研制了性能较好的NTD硅探测器。用它精确测定14MeV中子能量和作为γ射线计数器均取得了较满意的结果。其性能指标为:反向偏压1kV,漏电流≤5μA,26℃;对~(241)Am α源,FwHM为31-50KeV,26℃;对~(137)Cs 625 keV的内转换电子,FwHM为6.85LeV,-2℃。     

φ76mm×100mm BGO闪烁探测器在20 MeV以下能区的能量响应

用上海硅酸盐所提供的φ76mm×100mm BGO晶体制作γ闪烁探测器、用来探测???离子核反应中放出的10-100 MeV的γ射线,该探测器对~?Cs的0.661 MeV γ射线的?????14.2%。在加速器上用若干(p,γ)反应产生的单能光子测试探测器的能量响应,通过细致的数?拟合得到该探测器在20 MeV以下能区的能量响应和全能峰能量分辨率。对17.65 MeVγ射线。探测器的能量分辨率为4.1%。     

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.