环境样品γ射线自吸收修正因子与样品质量的相关性

本文探讨高纯锗（HPGe)γ谱测量环境样品时γ射线自吸收修正因子与样品质量之间的相关性。采用装于相同规格样品盒的8个不同质量的环境样品（海洋沉积物）和1个标准源基质材料（290g)，将一块发射多个γ射线的标准点源（152Eu 137Cs)放置在准直器上，用HPGeγ谱仪对不同能量γ射线测量8种不同质量的样品相对于标准源基质材料的自吸收修正因子F。将自吸收修正因子F与样品质量m进行回归分析，得到F－m直线回归方程，用此方法得到的修正因子对测量的IAEA标准参考物质样品的活度进行修正，得到令人满意的结果。     

铀样品丰度分析技术研究

用高纯锗半导体γ探测器测量了不同质量的球形高浓铀和贫化铀样品以及两者相组合模型.采用PCFRAM分析软件对测量数据进行了铀丰度分析,研究铀丰度的分析结果与测量时间、不同屏蔽厚度、样品质量和样品的组合模型的关系.结果表明:在一定条件下,测量时间的长短直接影响到分析结果的可靠性;分析结果与铀样品外是否加屏蔽体无关,而是取决于测量能谱中γ射线计数的统计涨落.在保证高质量测量能谱的前提下,可以准确地分析出铀材料的丰度;在高浓铀和贫化铀材料同时存在时,无法区分样品的丰度.     

土壤样品γ谱分析自吸收校正技术研究

用点源实验方法,表征了探测器晶体的结构参数,以此为基础利用蒙卡模拟计算了不同质量样品对各种能量γ射线的线衰减系数和探测效率,进而建立了75 mm×25 mm样品自吸收校正因子F(μ)的关系式;使用标准面源模拟体源不同高度的薄层,通过γ能谱测量得到体源不同高度薄层的探测效率与其高度的函数关系式ε(h),积分获得体源探测效率,进而建立75 mm×25 mm样品自吸收校正因子随γ射线线衰减系数的变化关系F(μ),面源实验建立的F(μ)关系式与蒙卡计算得到的F(μ)关系式趋于一致。以蒙卡计算模型为依据,拓展计算了75 mm×75 mm盒装土壤样品的F(μ)函数关系,并实验验证了计算结果的有效性。利用建立的F(μ)函数关系对取自某污染场址的多个土壤样品进行测量结果自吸收校正,建立了样品质量和自吸收校正因子的函数关系F(m),并给出土壤样品自吸收校正的技术方法。     

中子场及γ射线自吸收在PGNAA测量中的影响研究

在中子活化瞬发γ射线分析(PGNAA)技术测量中,被测样品内部中子场分布及γ射线自吸收对测量结果有一定影响。针对一套水溶液样品中有害元素的检测装置,通过对两种效应统一考虑并进行了理论计算,建立了一套相应的理论修正模型,并将其应用于检测装置的蒙特卡罗模拟计算结果中。结果表明,经该理论模型修正后,样品中中子场分布及γ射线自吸收对分析结果所造成的影响得到了显著改善。     

体源样品γ自吸收修正因子的蒙卡方法研究

采用相对法测量环境辐射样品的γ能谱时,待测样品与标准样品对γ射线的自吸收程度差异会导致测量结果不准确,需对待测样品进行自吸收修正.本文通过点源试验方法得到HPGe探测器晶体的实际结构参数,在此基础上使用蒙特卡罗方法寻找体源自吸收率与同能量外置点源透射率间的函数关系.该方法综合考虑了体源基质成份和密度对自吸收修正因子的影...     

大样品中子活化分析的理论依据和误差修正

中子活化分析(NAA)是最重要的核分析技术之一。目前,国内和国际上绝大多数NAA实验室只能对小样品(mg～g或μL～mL)进行分析。本工作概要介绍大样品中子活化分析的原理,重点介绍了由于体积增大而带来的中子注量率自屏蔽、γ射线自吸收等修正因子的算法,以及对样品不均匀性的修正方法。     

γ射线自吸收修正因子精确计算方法研究

对具有一定几何尺寸的样品进行γ谱分析时,样品自身对γ射线的吸收影响对核素含量的精确测量。本文在对比国内外关于自吸收修正因子计算方法的基础上,分析了被广泛采用的简化计算模型存在的问题及对修正结果的影响。基于混合蒙特卡罗模拟的思想,提出了自吸收修正因子的精确计算模型,并使用FORTRAN程序进行了随机抽样和积分计算,得到精确的自吸收修正因子。通过加标样品及不同质量标准源的对比测量,将精确计算模型与简化计算模型和无源效率校准软件计算结果进行了对比分析。结果表明,简化计算模型过高评估了自吸收干扰,而精确计算模型计算结果与实验测量结果及无源效率校准软件计算结果具有较好的一致性,相对偏差不大于5%。最后针对核电厂周围环境中主要关注的γ核素,使用精确计算模型得到了不同γ核素在土壤中的自吸收修正因子。     

用活化法无损测定金属铀样品中~(238)U的含量

238U作为一种重要的裂变材料,其含量的准确测定在裂变产额数据测量中具有重要意义。在四川大学2.5 Me V质子静电加速器上,利用T(p,n)3He反应产生的483 ke V单能中子照射金属铀样品,对照射后生成放射性核素239Np的特征γ射线进行测量,利用已知的238U(n,γ)俘获截面数据实现了对238U含量的准确测量。对影响测量结果准确性的因素做了细致分析,采用蒙特卡罗方法应用软件MCNPX(Monte Carlo N-Particle e Xtended)对中子的多次散射效应和中子注量衰减效应进行了修正,对γ射线在样品中的自吸收也进行了修正,修正后的实验结果是2.884 2 g金属铀含5.712 8×1021个238U原子,实验结果的不确定度是4.1%。     

聚乙烯样品源γ自吸收校正的MC模拟

介绍了一种放射性样品检测的γ射线自吸收校正方法。对聚乙烯为介质的均匀体源样品进行了无损透射测量和发射测量实验,并使用MCNP程序对透射测量和发射测量过程进行模拟,由透射测量得到样品对多个能量γ射线的线衰减系数,拟合得到线衰减系数随能量变化的特征方程,从而获取发射γ射线在样品中的线衰减系数以及自吸收校正因子,结合发射γ射线的探测效率,计算得到校正后的样品活度。验证实验表明:样品校正活度相对误差均在6%以内。     

14MeV中子活化分析法测定钢样品的透射比及氧含量

用14MeV中子活化分析相对法测定钢或其它金属的氧含量时,由于标准和样品基体的差异,会造成它们中子自屏蔽与γ自吸收的不同。为此,需引入透射比因子(transmittance)修正测得的结果。利用物质对中子屏蔽及对γ吸收的规律计算透射比不易准确,故大多针对具体的分析装置,采用实验方法测定。I.Fujii以及J.Hoste等人曾测定了纵向(端面)接受辐照的圆柱状样品的透射比,本工作则是对横向(侧面)接受中子辐照的圆筒状钢样品的透射比进行测定,并利用测得的结果完成钢中氧的活化分析。     

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.