LaBr3(Ce)探测器点源效率函数研究

点源与探测器相对位置发生变化时,探测效率会发生很大变化,确定探测效率随探测距、角度变化的函数关系有利于快速得到点源在任意位置处的探测效率。利用蒙特卡罗软件MCNP5模拟计算了¹⁵²Eu、¹³⁷Cs、⁶⁰Co点源在特定位置处的探测效率,与实验结果相比,最大误差不超过6%。基于MCNP5对3.81 cm LaBr₃(Ce)探测器做效率刻度,并计算了点源在探测器正面2π空间范围内不同位置处的探测效率,拟合了探测效率与角度和距离的函数关系。结果表明：点源探测效率最大值出现在与探测器轴线夹角90°处,随着探测距离和能量的增大,角度对点源探测效率的影响逐渐减小;空间位置对探测效率的影响实际上是对点源相对于探测器的空间立体角效率。基于效率函数可计算出特定能量γ射线在空间任意位置处的探测效率,对LaBr₃(Ce)探测器效率矩阵的求解及效率刻度具有一定的参考价值和指导意义。     

基于蒙特卡罗方法的XRF探测器立体角分析

为研究探测器立体角在X射线荧光(X-ray fluorescence,XRF)分析仪的设计对测量结果的影响,运用蒙特卡罗方法对XRF仪进行建模。结果表明,探测器脉冲计数随着探测器与样品之间距离的增大指数衰减;随着探测器立体角的增大,特征峰计数非线性增大,源峰探测效率指数递减;探测器本征探测效率与探测器立体角无关。本文研究方法和结论可为一些XRF仪的设计提供参考。     

基于半球型碲锌镉探测器的多功能剂量率仪适用性研究

常用的剂量率仪主要针对能量在50keV以上的强贯穿γ射线,半球型碲锌镉(CZT)探测器对中低能γ、X射线具有较好的探测效率和能量分辨率。本文从能量范围、能量分辨率、环境适应性和角响应等方面阐述基于半球型CZT探测器作为多功能剂量率仪的适用性。除存在角响应以外,其他方面均说明基于半球型CZT探测器的多功能剂量率仪较常用的场所辐射监测仪器(如电离室等)具有更大的优势,其不仅能测量周围剂量当量率,还可进行放射性核素识别。本文提出了利用两个半球型CZT探测器共阳极的解决方案来改善其角响应问题。     

平板高纯锗探测器几何参数修正的解析方法

本文推导了1个用于计算平板高纯锗探测器对点源发射光子的探测效率的数值积分公式,并应用此积分公式进行了高纯锗探测器的几何参数修正。将²⁴¹Am、¹³⁷Cs点源分别置于平板探测器前端的不同距离（1~20 cm）处进行实验测量,以探测效率的实验结果为拟合真值,利用积分公式通过加权最小二乘拟合获得该探测器的几何参数。将修正后的参数应用于MCNP模拟计算,对59.5及661.6 keV光子,在1~20 cm探测距离范围内,探测效率的模拟值与实验值之间的相对偏差<1%。研究表明,此解析方法实现了对探测器几何参数的快速修正,结果准确可靠。     

医疗场所空气中碘-131在线探测系统模拟设计

为了实现无富集条件下对碘-131的快速精准测量,提出了针对医疗场所空气中碘-131的γ、β联合测量方法。通过Geant4建立探测系统模型,模拟研究探测系统对碘-131释放的β粒子和γ射线进行探测,其中NaI探测器和塑料闪烁体探测器分别实现对γ射线和β射线的测量。模拟计算表明,探测系统获取的γ全能峰计数、β计数与碘-131浓度之间存在线性关系。系统可首先通过获取γ能谱分析碘-131特征峰实现碘-131识别,利用γ射线全能峰计数与β射线计数之间的线性关系确定β射线贡献是否仅来自于碘-131,然后利用β射线的高探测效率进行快速测量。模拟计算探测系统测量1 h,其双3英寸NaI探测器的探测效率为1.7%,其MDC可达到19.59 Bq/m³,其塑闪探测器的探测效率为36%,MDC为7.93 Bq/m³,均显著低于38.50 Bq/m³。基于γ全能峰计数和β计数的联合计算公式计算的碘-131的浓度,相对误差≤0.6%。提出的探测系统充分利用了β射线探测效率高和γ能谱能量识别能力强的优点,通过γ能谱全能峰计数和β计数测量可实现碘-1...     

基于SiPM的硫化锌闪烁探测器设计与研制

基于SiPM的优良性能和特征,以SiPM和硫化锌闪烁瓶组合探测方式设计探测器。该探测器包括前端信号探测与采集电路和温度控制系统。信号探测与采集电路以交流耦合方式设计前置放大电路,经单道脉冲幅值甄别电路输出计数脉冲用于放射性含量计算。温度控制系统依据分布式测温模块反馈结果,配合模糊PID算法调节半导体制冷器输出功率,实现探测器实时温度调控。实验结果表明,在温度控制系统作用下,当环境温度为40℃时探测器的探测效率由80%提升至94%,其稳定工作的动态温度范围由(-15～30)℃扩展到(-15～40)℃,基本满足野外实际环境的应用需求。     

LaBr_3:Ce探测器对低能γ射线角响应研究

建立以探测器前表面中心和探测器体心为参考原点的两种几何模型,研究了Saint-Gobain Brillan Ce380探测器对~(241)Am、~(133)Ba、~(137)Cs源γ射线在15 cm、25 cm、35 cm处由0~90°范围内入射能量沉积脉冲高度谱,通过源峰探测效率的差异表征角响应的变化。实验结果表明:该探测器对低能γ射线响应随入射角度的增大呈递减趋势,源峰探测效率最大变化约达30%,并随源距离的增加各向异性程度逐渐减弱。此结果可为LaBr_3:Ce探测器检测未知核材料及其剂量水平提供修正参考。     

井型4πβ+4πγ活度测量装置

4πβ+4πγ活度测量装置由4π流气式正比计数器、井型NaI(Tl)探测器和HPGe探测器构成。将4π流气式正比计数器放于HPGe探测器上,插入井型NaI(Tl)探测器井中,实现了β射线探测效率、活度和γ分支比的同时测量。测量了60Co、137Cs和166mHo的放射性核素活度,结果分别为:127.64(1±0.34%)、191.68(1±0.27%)和130.17(1±0.21%)Bq/mg,与国内外比对结果符合得很好;同时测量了137Cs和166mHo的主γ射线分支比,与文献值在不确定度范围内一致。     

新型低本底α/β测量系统设计

设计了一套新型低本底α/β测量系统。该系统采用ZnS(Ag)薄板复合塑料闪烁体作为主探测器,平板形塑料闪烁体作为反符合探测器,实现样品中总α和总β的同时测量。利用ARM架构的MCU作为系统运行核心,FPGA硬件电路作为数据采集单元,基于脉冲宽度甄别方法实现测量系统的α/β脉冲甄别。对该系统进行了主要性能测试,测试结果表明:测量α粒子时,本底为0.003 min~(-1)·cm~(-2),对~(239)Puα标准平面源的探测效率为92.5%,α对β道的串道比为0.87%;测量β粒子时,本底为0.072 min~(-1)·cm~(-2),对~(90)Sr-~(90)Yβ标准平面源的探测效率为62.0%,β对α道的串道比为0.03%。     

行人放射性快速识别仪谱数据处理软件设计

介绍了行人放射性快速识别仪中实现谱数据部分快速处理的软件设计。利用FPGA内嵌硬件DSP模块和硬件资源,构建了浮点乘和累加运算单元、浮点除法运算单元、浮点指数运算单元和浮点开方运算单元,在0.7 s内完成谱数据处理运算,使快速识别仪能在1 s内完成γ辐射探测、同位素识别及自动分类,最低可探测活度41.9 k Bq,可用于放射性物质的快速检测。     

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.