D-T脉冲中子发生器随钻中子孔隙度测井的蒙特卡罗模拟

利用蒙特卡罗方法模拟研究了D-T脉冲中子发生器和241Am-Be中子源产生的中子与地层的作用过程,以探讨D-T脉冲中子发生器在随钻中子孔隙度测井中的应用价值。模拟结果显示,使用这两种中子源,热中子计数均随源距增加而呈指数下降;孔隙度较小时,两者的计数差异较小,当地层孔隙度达到40%时,D-T脉冲中子发生器产生的热中子和超热中子计数均比²⁴¹Am-Be中子源高很多,其分布范围也更宽,近探测器的源距选择20～30 cm,远探测器的源距选择约60～70 cm;D-T脉冲中子发生器用于中子孔隙度测井时对地层孔隙度的灵敏度降低,而相同源距条件下探测深度几乎不变。以上结果提示,利用D-T脉冲中子发生器可以进行补偿中子孔隙度测井,在增加源距的同时既可以保证计数统计性,又可以提高灵敏度和探测深度,在随钻测井仪器设计中可以取代²⁴¹Am-Be中子源。     

小型中子照相装置慢化体的研究

文章研究用混合D-T束密封中子发生器进行中子照相的14MeV中子慢化问题,提出了用高密度聚乙烯和铅相结合慢化14MeV中子的结构,实验证实,在源附近加一定厚度的铅层可以把热化比降低三分之一左右。这种结构的热化比是用水慢化14MeV中子的热化比的1/2—1/3。慢化体加铅后对中子束镉比的影响并不很大。     

中子发生器的纳秒脉冲聚束系统

为了用飞行时间法精确测量中子能谱,从俄罗斯Efremov电物理所引进了一台纳秒脉冲中子发生器。该中子发生器采用聚束系统产生纳秒脉冲束流,其中的纳秒脉冲信号源、高频聚束电源、负反馈调节系统等关键设备都是自主研制的。采用双扫描技术解决了聚束电源电压过高的问题,采用负反馈技术使纳秒脉冲聚束系统长期稳定工作。为了测量纳秒脉冲束流,研制了快脉冲同轴靶测量装置,测得中子发生器的离子束流脉冲半高全宽为1.5 ns,脉冲重复频率为1kHz-4MHz,束斑直径为10 mm。由于采用了电子回旋共振离子源(Electron Cyclotron Resonance,ECR),所以该中子发生器具有发射度小、能散小、无灯丝、可长时间连续工作的优点,是中子物理研究的良好实验平台。     

紧凑型D-D中子发生器控制系统设计与实现

紧凑型D-D中子发生器为工业物料中子活化分析提供稳定可靠快中子源,其控制系统需要实现对加速器现场多设备远程参数调节和状态监测,保证中子发生器持续稳定运行,采用PC机加智能仪器构成的分布式结构,设计开发了一套基于Lab VIEW的综合控制系统,将My SQL数据库接入控制系统,实现中子发生器各设备主要运行参数的保存与查询。系统测试稳定,并成功应用于该中子发生器的调试和实验中。     

HINEG强流氘氚中子发生器方案设计分析

HINEG(High Intensity Neutron Generator)中子发生器是正在设计建造的直流/脉冲两用型强流氘氚聚变中子发生装置。本文给出装置的总体方案,并对其主要设计特点进行分析。HINEG直流中子强度的最高设计指标为3×1013 n/s,脉冲中子脉冲宽度的设计指标小于1.5ns,束流光学计算结果表明,总体方案设计可以满足设计指标要求。系统设计的主要特点包括螺线管透镜选束聚焦、高梯度均匀场加速管加速和高能段切割的脉冲化方式。     

400 kV强流中子发生器的物理设计

对400 kV强流中子发生器进行了物理设计。采用Poisson/Superfish软件对中子发生器高压电极和加速管的电场分布进行了模拟,结果显示,各关键区域的空间电场最大值远低于击穿电场限值。以强流束旁轴包络方程为基本模型,发展了强流束传输系统束包络的计算机模拟程序IONB1.0,模拟了中子发生器传输系统中40 mA的D束流包络。结果显示,设计方案中所采取的两间隙高梯度加速结构有较强的聚焦性能,能有效抵消强流束空间电荷效应造成的束流发散,加速管出口处的束包络半径约3 cm,由加速管出口处的空间电荷透镜和三重四极磁透镜组成的传输系统能将束流聚焦在约140 cm处的靶上,且束斑直径小于2 cm。     

600kV ns脉冲中子发生器的一些相关问题的研究

就中子物理飞行时间技术对脉冲中子发生器的需要，对中国原子能科学研究院６００ｋＶｎｓ脉冲中子发生器的聚束和切割性能的某些参量进行分析和计算，将结果与实验进行比较，并把它们用于脉冲化装置的调试     

ECR离子源实验台的研制

介绍了ECR离子源实验台的工作原理、基本结构和研制过程。作为实验和测试平台,ECR离子源实验台可以很方便的调整离子源各参数,在靶上得到好的束流品质。通过对部件的改进和调试,解决了束流较小的问题,使ECR离子源工作在最佳状态。上述结果可用于中子发生器的运行调试。因此,ECR离子源实验台是强中子发生器所必需的实验设备。与国内外的ECR离子源相比,ECR离子源实验台主要着眼于中子发生器的模拟实验,在结构上强调小型化、实验平台化,在功能上要求能够在线测量许多重要参数。测量结果表明,ECR离子源实验台技术指标达到设计要求。     

两种中子源条件下补偿中子测井仪探测器设计方法

使用同位素中子源或中子发生器将直接影响补偿中子探测器的参数设计,论文主要探讨了探测器源距设计方法,通过3700中子刻度筒实验,比较了两种中子源条件下的实验结果,采用数据拟合方法,给出了将测量得到的计数率比值转换为地层孔隙度的数学模型。结果表明,可以用中子发生器代替同位素中子源实现补偿中子测井。     

D-T快中子照相准直屏蔽体设计及中子束特性的模拟研究

设计一个用于氘氚(D-T)快中子照相的准直屏蔽体系统,对D-T中子发生器快中子在准直屏蔽体材料中输运的MCNP模拟研究,给出准直中子束的中子能谱、注量率及均匀性、γ射线能谱和γ射线注量率等重要参数.模拟结果显示,用D-T中子发生器中子源和合理的准直屏蔽体系统可得到快中子照相所需的准直快中子束.     

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.