HPGe探测器死层厚度及点源效率函数研究

在层析γ扫描分析方法的效率矩阵求解过程中,建立准确尺寸的HPGe晶体计算模型对所求的探测器效率矩阵准确性有很大影响。在使用原始的实验探测器晶体尺寸建立的模型进行探测效率计算时,发现计算与实验所得的探测效率最大误差达19%。调整探测器计算模型的死层厚度可使计算结果准确度得到很大改善。研究发现,死层厚度与各测量点相对误差平均值存在线性关系,在此基础上提出一种可快速确定最优死层厚度的修正方法。使用调整后探测器晶体尺寸,计算出不同位点源位置不同射线能量下的探测效率,拟合出探测效率与点源位置及射线能量的函数关系,用于快速求得探测效率矩阵。     

HPGe探测器对环状γ面源探测效率刻度研究

天然铀分解模拟装置中铀的相关反应率是研究混合堆包层设计宏观中子学的重要数据,采用活化法测量相应反应率的过程中必须对环状天然铀箔片的探测效率进行精确刻度。为了研究快速有效刻度HPGe探测器探测效率的方法,利用一系列标准伽马点源测量了轴线上6cm高度位置的点源探测效率曲线,在蒙特卡罗程序MCNP5中调整探测器内部结构参数,同时对HPGe探测器的探测效率进行模拟计算,在计算结果与实验结果能较好拟合的情况下推算探测器的死层厚度、冷指长度和半径等参数的实际尺寸。利用计算的尺寸模拟计算探测器对环状伽马源的探测效率,计算结果与实验结果在较宽能量区域(200~1 400 ke V)内在4%内符合。     

应用蒙特卡罗方法表征HPGe探测器

采用蒙特卡罗方法计算HPGe探测器对光子的探测效率,需对计算模型参数进行确定。使用蒙特卡罗模拟计算和实验测量相结合的方法,对晶体死层厚度及冷指尺寸进行了表征。结果表明,使用此方法确定晶体参数模拟光子的探测效率,在59.54～1408.1keV光子能量范围内,计算效率与实测效率相对偏差在5%以内,并进行了实验验证。     

蒙特卡罗模拟确定HPGe探测器点源效率函数及参数

在探测器晶体体积一定的情况下,HPGe探测器点源效率主要由γ射线能量、角度和探测距决定。利用极坐标对点源进行空间定位,试验测试了不同角度和探测距条件下137Cs和60Co点源的γ能谱,同时采用MCNP程序模拟计算HPGe探测器不同角度与探测距条件下γ点源效率,并与实验值进行对比和校正。结果表明,探测角度在0-9π/24,γ点源效率模拟值与实验值之间全能峰净计数的相对偏差均在8%以内。最后对γ点源效率模拟值进行多元非线性回归,确定了在特征γ射线能量下,以角度和探测距为因变量的点源效率函数及其参数。     

HPGe探测器点源效率与其空间位置的函数关系

本文采用蒙特卡罗(MCNP)模拟与实验相结合的方法,计算了HPGe探测器(美国Ortec公司产品,相对效率40%,对1332keV的分辨率为1.8keV)对空间不同位置、不同能量点源的探测效率,对Masayasu等[1]提出的点源径向表达式作了修正,改进了与实验值(或MC模拟值)的一致性;给出了HPGe探测器效率随点源位置变化的解析表达式;证明了应用MCNP模拟方法确定探测器对于点源的探测效率函数的可靠性和实用性,也有助于对体源效率的测量和计算。     

空间任意位置点源效率函数及参数的确定

采用蒙特卡罗(MCNP)模拟与实验相结合的方法,计算了HPGe探测器对空间不同位置、不同能量点源的探测效率.根据模拟计算结果,通过数值拟合方法,确定了HPGe探测器对点源137 Cs和60Co的探测效率函数及其参数,并对实验结果进行验证.研究表明,应用蒙特卡罗模拟方法确定HPGe γ探测器对于点源的探测效率函数及其参数是一种简便、有效的方法.     

基于数值积分法的无源效率刻度方案研究

无源效率刻度技术一直是核分析领域研究的热点,但现行无源效率刻度技术需依据指定探测器进行订制。基于伽马射线指数衰减规律推导了圆柱体探测器周边任意位置点源探测效率的数值积分公式。依据探测器与待测物几何结构的轴对称性和伽马场叠加原理,构建了实验室常用几何结构体源的探测效率计算方案。在笔记本电脑(CPU:i5-8250U@1.60 GHz;RAM:8.0 GB)上应用上述方法计算HPGe圆柱体探测器对马林杯水体和NaI圆柱体探测器对圆柱体土壤内多种能量特征伽马射线的探测效率,发现探测效率计算值与实验值之间相对偏差为-4.9%～3.9%,且计算时长最大为35.78秒,证实本方法能准确、快速地实现圆柱体探测器的无源效率刻度。且本文推荐方法在探测器尺寸变化的情况下仅需修改相应参数,具有很强的通用性。     

惰性气体流出物离线监测仪的三种效率校准方法研究

介绍了3种替代的效率校准方法,并分别用它们计算1台HPGe谱仪测量1枚等效气体源时的探测效率曲线。蒙特卡罗（MC）法建立的探测器模型中所用尺寸参数为厂商提供的值,其计算结果不可靠,与实验值的最大相对偏差达130%。数值积分法和代表点法皆用了1枚多γ核素标准点源,同时还借助了MC模拟计算。当γ射线能量在60～1 836 keV范围时,代表点法计算结果的相对偏差≤±6%,数值积分法计算结果的相对偏差≤±4%,这两种方法均能满足现场工作对不确定度的要求,其中代表点法更易实施。     

溴化镧探测器效率刻度与晶体表征

利用三种不同的放射性标准点源对溴化镧探测器的能量与道址关系曲线、能量与半高宽、全能峰探测效率曲线进行了实验研究;然后利用蒙特卡罗方法和实验探测效率曲线对溴化镧探测器的尺寸进行了表征,建立计算模型。根据计算模型,模拟计算在不同位置、能量区间在100~1 500 keV范围内的γ射线的全能峰探测效率。模拟结果与实验结果的相对偏差绝大部分处于±5%以内,说明计算模型是准确可靠的。     

蒙特卡罗方法计算用于低能光子测量的高纯锗探测器的效率

在内照射活体测量中,为了用蒙特卡罗方法计算探测器对光子尤其是低能光子的探测效率,需要对探测器准确建模。通过使用蒙特卡罗模拟计算和实验测量相结合的方法来准确确定低能光子高纯锗探测器晶体的死层厚度、半径和长度;结果表明使用此方法确定的晶体尺寸来模拟计算探测器效率,在17．5～662keV光子能量范围内,低能光子高纯锗探测器探测效率的模拟计算结果与实验结果比较,相对偏差平均小于1．0％,最大为3．2％。     

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.