锗γ能谱测量中的符合相加修正

本文介绍了锗γ能谱测量中符合相加修正的原理和方法,给出了修正公式。分别计算了不同几何条件下两个锗探测器对一些放射性核素的符合相加修正因子,估计了符合相加修正因子对活度测量结果的误差贡献。     

γ射线级联衰变符合相加修正方法研究

γ射线级联衰变引起的符合相加干扰可导致被测量γ射线全能峰计数增加或减少,从而使测量结果偏离真实值。本文从级联符合相加产生的机理出发,以~(134)Cs为例研究了级联符合相加修正因子的数值计算方法。基于蒙特卡罗计算程序MCNP给出了γ射线全能峰效率和总效率的模拟计算方法。通过实验测量和软件计算验证了符合相加修正因子数值计算方法的准确性。针对核电厂周围环境监测中主要关注的人工放射性核素,计算了不同环境介质中γ核素测量的符合相加修正因子。计算结果表明,对于气溶胶、生物灰样品中核素~(110)Ag~m、~(134)Cs符合相加干扰可达20%以上,而对于全能峰效率相对较低的土壤样和水样符合相加干扰可大于10%,其余核素也不同程度地存在符合相加干扰。本文研究结果为γ放射性核素的准确测量和误差来源分析提供了技术参考。     

γ能谱测量中符合相加修正蒙特卡罗模拟计算程序的实验验证

本工作采用简便易行的符合相加修正实验方法，即远近比较法，对本实验室自行编制的、用于修正HPGeγ能谱测量中符合相加因子的蒙特卡罗模拟计算程序进行了验证。     

γ能谱符合相加效应修正方法及影响因素

在辐射环境质量监测中,多能核素的级联符合相加效应是影响γ能谱活度测量准确性的重要因素之一,为了提高待测样品分析的准确性,对结果进行符合相加修正是十分必要的。以¹⁵²Eu核素为例,根据峰总比不变性特点,获得探测器峰总比拟合公式,联合符合相加修正公式,全能峰效率公式,计算了¹⁵²Eu核素的符合相加修正因子,进一步采用Genie 2000符合相加蒙特卡罗程序对液体体源的¹⁵²Eu核素进行了符合相加修正。点源的修正结果与真值的相对偏差小于6%,体源修正结果与真值的相对偏差在±4%以内。通过点源符合相加修正因子与源到探测器距离的线性关系,可以得到符合相加效应可忽略的最小测量距离;体源样品的符合相加修正结果表明：同一介质的样品,高度越高,符合相加修正因子越小;自吸收效应会在低能端对样品的有效立体角产生较大影响,从而影响样品的符合相加修正因子。峰总比不变性与衰变纲图相结合的数值修正方法,不需要对不同位置处的点源总效率进行测量,与蒙特卡罗程序法相比,该方法无需对探测器进行工厂表征,不用对体源介质、密度和形状等参数进行描述;舍弃级联符合较...     

符合相加修正因子随样品厚度的变化

本文用蒙特卡罗方法计算了以水为介质的＾１５２Ｅｕ源几种能量的γ射线在不同体源厚度时的符合相加修正因子，同时用实验进行了验证。     

蒙特卡罗方法计算高纯锗γ谱仪对面源的探测效率和符合相加修正

本工作使用蒙特卡罗方法，借助于EGS4软件包，通过自编用户程序，研究γ谱仪对面源的效率刻度和符合相加修正。该程序在擦拭与气溶胶样品的实际测量中，可解决缺少标准效率刻度源问题，并使得符合相加修正计算简单实用。     

符合相加的MCNP计算

提供了一种新的计算符合相加修正因子的方法,并将该方法用于点源和体源的情况,分析符合相加因子随源与探头距离及样品厚度的变化规律.     

~（134）Cs衰变γ射线发射率的测量及一个简单的符合格加修正方法

借助一套高性能的多道计算机γ谱仪系统，精确测量了￣（１３４）衰变γ射线的绝对发射率和相对发射率。并且使用了一个简单的符合相加修正方法，对￣（１３４）Ｇｓ衰变的两条主要的级联γ射线的符合相加进行了修正，获得了较好的结果。     

^1^3^4Cs衰变γ射线发射率的测量及一个简单的符合相加修正方法

借助一套高性能的多道计算机γ谱仪系统，精确测量了＾１＾３＾４Ｃｓ衰变γ射线的绝对发射率和相对发射率。并且使用了一个简单的符合相加参修正方法，对＾１＾３＾４Ｃｓ衰变的两条主要的级联γ射线的符合相加进行了修正，获得了较好的结果。     

HPGeγ谱仪110mAg符合相加修正因子实验测定与拟合计算

本文介绍了广东省环境辐射研究监测中心(GERC)辐射分析室用实验方法测定三台不同效率的HPGe γ能谱仪^110mAg符合相加修正因子的结果,并依据其中一台谱仪的实验结果进行数据拟合,得到^110mAg 657．76keVγ射线符合相加修正因子c与^137Cs 661．66keV γ射线效率的函数关系。利用这一函数关系,得到另外两台γ谱仪的c的计算值,与其实验值相比较,最大相对偏差为6．4％。同时,还使用广东大亚湾核电站环境实验室的部分数据,对此拟合函数进行了验证,相对偏差在6．2％以内。     

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.