平面型硅快中子剂量探测器初步研究

介绍了平面型硅快中子剂量探测器,初步探索了探测器的中子剂量响应与PN结长和结宽的关系。基于239Pu-Be中子辐射实验结果,可以得出探测器电压随中子剂量线性变化的结论。对探测器等效电阻进行了计算,给出了测试电流为1~10 mA时平面型硅快中子剂量探测器的电流、电压和中子剂量的关系式。     

快中子活化分析

快中子活化分析主要指的是利用粒子加速器产生的快中子对于元素进行定性和定量测定的一种核分析技术。本文简要叙述了快中子活化分析,主要是14MeV中子活化分析的基本原理、分析测量技术、方法特点和应用范围。特别就快中子活化分析在核材料和核燃料方面的应用作了较为全面的介绍。并且对于快中子活化分析的现状、今后的发展动向和应用前景也作了简要的评述。     

宽基硅二极管快中子剂量仪元件的研制情况简介

一、引言为了解决有中子与γ射线的混合辐射场中快中子剂量测量的问题,巴特尔(Battelle)实验室早在1957年就开始了对γ射线和热中子不灵敏的半导体快中子剂量仪系统的研究工作。电导调制下使用的宽基硅二极管,在性能上与设备的简便程度上都表现了其独特的优越性。在国外,在这方面的研究工作一直持续到现在,我们自己在这方面的工作,还处于初步尝试的阶段,仅在这里作一简单的介绍。     

快中子活化分析

快中子活化分析主要指的是利用粒子加速器产生的快中子对于元素进行定性和定量测定的一种核分析技术。本文简要叙述了快中子活化分析,主要是14MeV中子活化分析的基本原理、分析测量技术、方法特点和应用范围。特别就快中子活化分析在核材料和核燃料方面的应用作了较为全面的介绍。并且对于快中子活化分析的现状、今后的发展动向和应用前景也作了简要的评述。     

隐藏爆炸物检测装置快中子辐照安全分析

为推广隐藏爆炸物检测装置在反恐领域的应用,对快中子辐照炸药、食品及药品的安全性进行了分析。通过蒙特卡罗方法建立了装置的快中子辐照炸药安全性评估模型。通过能量沉积计算及炸药起爆机理分析可知,快中子辐照炸药不会产生爆炸的危险。采用剂量分析法对快中子辐照食品及药品的安全性进行了分析,结果表明,在隐藏爆炸物检测装置的快中子辐照条件下,食品及药品的辐照剂量在国家和国际限定的标准内,快中子辐照食品及药品的安全性是可接受的。     

PIN型快中子剂量探测器的结构研究

介绍了不同结构比例的PIN宽基硅二极管快中子剂量探测器对^236mPu-Be中子源的剂量响应测试结果。通过对实验结果进行分析,建立了探测器的等效电路模型,得出了探测器的剂量响应与结构比例参数(d／A)近似成线性关系的结论。     

基于BM3D算法的快中子图像降噪方法

在快中子照相过程中,由于受到各种因素影响,快中子图像严重降质,呈现大量噪声,不利于无损检测和后续的定量分析。通过噪声分析得出了快中子图像的噪声统计分布符合高斯噪声模型,探讨了将BM3D算法应用到快中子图像降噪处理的方法。实验结果表明,BM3D算法不仅能够有效滤除快中子图像的噪声,而且保护了图像的细节和边缘信息,可为快中子图像的降噪处理提供参考。     

探测快中子的新技术

本文概述了近年来探测快中子的新技术，它们分别是：抑制γ射线、热中子和带电粒子的符合谱仪；高分辨宽能量范围正比计数器的＾３Ｈｅ夹心谱仪；含氢的纤维闪烁体用于抑制γ射线、中子位置分布和中子能谱测量；及含锂的纤维玻璃闪烁体用于长中子计数器测平均中子能量；中子的直接探测；用于中高能和重离子核物理的多元件阵列快中子探测器和极化仪；用于核核查的中子源影像探测器；高入射氘核能量和高能中子的伴随粒子技术等７个方面     

快中子能谱在线测量的反冲质子望远镜响应模拟研究

快中子能谱是基于散裂中子源开展大气中子单粒子效应研究的关键输入参数,在线测量宽能区快中子能谱在近散裂靶位置面临飞行时间法不确定度大、中子通量高、本底干扰强等问题。设计了反冲质子望远镜(RPT)系统,利用Geant4模拟了20～200 MeV中子轰击不同厚度聚乙烯转换靶产生的反冲质子产额、角分布以及能谱,为优化探测系统设计提供了指导依据。通过模拟硅探测器与新型快响应CLLB闪烁体组成的二重符合RPT系统对入射中子的响应,分析了影响探测系统探测效率和能量分辨率的因素,确定了聚乙烯转换靶厚度为1 mm、符合质子探测器摆放角度为26.6°和探测器尺寸等重要参数,得到了RPT系统的中子响应函数矩阵,并计算了其探测效率达10-5,对高中子通量和复杂本底干扰环境下的快中子能谱在线测量具有指导意义和参考价值。     

快中子照相MCNP模拟计算

正快中子照相是近些年新开展的一种照相技术,与热中子照相相比,快中子照相快中子具有能量较高、与物质作用截面较小、穿透能力强等特点,快中子穿过较厚被测样品材料时,通过记录出射的快中子可检测出物体内的元素空间分布、材料结构上差异等信息。本工作利用MCNP模拟计算了2.45 MeV中子穿过不同厚度聚乙烯样品及金属样品后的计数情况(图1),样品出射中子选用塑料闪烁体进行探测,实物如图2所示。对2.45 MeV快中子成像分辨率及塑料闪烁体探测     

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.