K荧光X参考辐射及其照射量测量

按国际标准ＩＳＯ４０３７研制的Ｋ荧光Ｘ参考辐射，性能基本符合该标准的要求，其能量范围为８．６４－９８．４ｋｅＶ。用校准过的薄窗电离室测量了参考辐射的量率。该参考辐射已用于校准Ｘ，γ剂量仪并剂量率仪并测定其能量响应。     

几种环境剂量率仪的刻度

环境辐射监测,近年来受到国内外普遍重视,各种测量仪器也相继出现。目前已采用高气压电离室,环境闪烁剂量仪,热释光剂量仪等,尽管形式多样,但在使用前都要进行γ照射量率刻度以及能量响应实验测定,以便能较准确地反映环境辐射场的照射量的分布。环境辐射主要成份是宇宙射线,陆地天然γ辐射,人工同位素的大量应用及核爆引起的污染。环境辐射能潜较为复杂,这就对测量仪器能量响应有所要求,其中电离室型仪器以及有能量补偿的塑料闪烁剂量率仪是二种能响性能较好的仪器。本文就球     

固定式环境γ辐射剂量率仪现场校准技术

固定式环境γ辐射剂量率仪是承担环境连续监测任务的主要设备,不便于拆卸送往计量实验室进行校准检定,且送检周期较长,影响连续监测点数据的连续性。为按期校准固定式仪表,本文结合蒙特卡罗方法研制了能量补偿型高气压电离室和便携式137 Cs照射装置,利用天然本底辐射(陆地γ射线和宇宙射线)和便携式照射装置产生的137 Csγ射线参考辐射对固定式环境γ辐射剂量率监测仪表开展现场校准实验。结果表明,采用环境比对和现场照射的方法能较好地解决固定式环境γ辐射剂量率仪的校准问题,现场所得校准因子与标准实验室中校准因子的相对偏差小于5%。     

低剂量率X射线辐射质的建立与仪器校准

辐射环境监测仪器的校准是评价仪器性能、保证量值准确可靠的重要方式。为了解决剂量仪表在低剂量率条件下的量值溯源问题,在X射线辐射场中通过进一步增加附加过滤的方式,建立了55 kV、70 kV、100 kV、170 kV和240 kV参考辐射质并测量其能谱,运用序蒙特卡罗程序EGS（Electron Gamma Shower）模拟各辐射质的能谱,计算出辐射质半值层及平均能量,模拟能谱与实测能谱的平均能量相对偏差不超过1.6%。利用大体积球形电离室完成参考点处空气比释动能率的测量,并对常用的辐射环境监测仪器进行了校准。结果表明：随着附加过滤的增加,剂量率逐渐减少,所建立的辐射质剂量率范围为606～4 451 nGy·h^-1,不确定度为6.0%（k=2）;高气压电离室、6150AD剂量率仪校准测量结果不确定度为7.0%（k=2）。     

高气压电离室能量响应特性的蒙卡方法优化设计

环境γ辐射监测用的高气压电离室要求具有较平的能量响应,以便提高其对环境γ辐射剂量率测量结果的准确性。论文利用MCNP蒙卡程序研究了高气压电离室对不同能量光子的响应特性,模拟研究了不同材料、不同厚度和不同面积能量补偿片对高气压电离室能量响应特性的作用规律,并在标准参考辐射场中进行刻度。根据其作用规律指导对高气压电离室外壁进行能量补偿的设计,解决了高气压电离室对不同能量γ射线响应不同的技术难题。计算和刻度结果表明:厚度为2 mm,屏蔽面积65%的锡片能够使高气压电离室在60 ke V~1.5 Me V之间的响应相对于137Cs的偏差在±30%以内,满足设计要求。     

组织等效电离室性能模拟分析

采用对中子和γ辐射具有相似灵敏度的组织等效电离室与对中子不太灵敏而对γ辐射灵敏的无氢电离室配对,组成双电离室探测器,测量反应堆混合场中的中子和γ剂量率,具有较高的测量精度。为给双电离室研制工作提供理论依据,本工作采用MCNP程序对组织等效电离室在不同条件下的γ射线能量响应、灵敏度及其影响因素进行模拟。模拟结果与文献参数比较,一致性较好。     

玻璃管CaSO_4 Tm热释光探测器用于低水平辐射测量的初步研究

本文叙述了玻璃管 CaSO_4:Tm 热释光探测器(TLD)用于低水平辐射测量的初步研究情况。用本探测器对山西晋祠山洞铅室内的辐射本底以及本所环境本底辐射选点进行测量,并同 PTB-7201型闪烁剂量率仪和 NCIRP 圆柱形高气压电离室的测量结果进行了比较。     

用于两种能量X射线剂量率监视系统的研制

针对能量可切换的无损检测加速器的剂量率在线监视系统，能够实现在不同能量下准确反映加速器输出的X射线剂量率。采用高灵敏度的传感器采集、积分并放大电离室输出的信号，输出给PLC，PLC的模拟量模块采集后得到量化的数值。剂量仪进行标准传递校准后，用来测试X射线剂量率。在高能、低能两种状态下分别测试得到两条校准曲线，拟合出相应的系数，     

γ辐射剂量率仪对宇宙射线响应及校准因子的间接校准

通过已测定和未测定宇宙射线响应的γ辐射测量仪在天然环境辐射场中的比对测量,可以确定辐射测量仪的宇宙射线响应及校准因子。选择美国通用电器公司生产的高压电离室RSS-131环境辐射监测仪作为量值传递仪器,对BH3103B便携式X-γ剂量率仪和6150闪烁体探测器γ辐射测量仪进行宇宙射线响应和校准因子的间接校准,与广东省辐射剂量计量检定站所检定的结果比较,校准因子的相对偏差分别为-2%和0;与在万绿湖对宇宙射线空气吸收剂量率的实测值比较,宇宙射线响应的相对偏差分别为-3.6%和3.1%。结果基本一致。     

全国环保系统环境γ辐射剂量率测量比对

全国环保系统于2002年在四川进行了γ辐射剂量率测量比对．比对结果表明．以高压电离室的测量结果平均值作为参考值．国产的BH型仪器测量数量大多偏低．国产JW型仪器测量数据大多偏高．手枪型小闪烁体剂量率仪测量结果的相对标准差较大。通过这次比对．基本摸清了全国γ剂量率测量仪的性能状况．为今后开展测量比对积累了经验。     

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.