蒂罗尔州西部阿尔卑斯山区室内高氡浓度

在奥地利蒂罗尔州西部一个村庄(Umhausen,居民2600)测量到了少有的室内高氡浓度,并发现肺癌死亡率比蒂罗尔州总人口(居民620000)的死亡率要高。在(?)tztaler Ache和Hairlachbach 2条河之间的地区发现氡浓度的年平均值特别高,该区地质为花岗片麻岩大滑坡的冲积扇(A区,一楼的年平均中值为1868Bq·m~(-3));其他村庄氡浓度比较低(B区,一楼的年平均中值为182Bq·m~(-3))。在这些中值的基础上,根据ICRP模型计算了年照射量(A区:58.8×10~5Bq·h/m~3;B区:5.7×10~5Bq·h/m~3)。利用从蒂罗尔州癌症注册处收集的数据确定了标准年龄和性别的肺癌死亡率(A区:6.17;B区:1.43)。     

广东省居民室内外空气中氡(气土)及其子体α潜能浓度水平及居民受照剂量

本文报道了1984年7月至1986年7月间对广东省(包括海南岛,但不包括西沙和南海诸岛)居民室内外空气中氡(气土)及其子体α潜能浓度的调查情况。布设测点时参考了地表γ辐射剂量率水平分布,将全省分为6个调查测量区域,共布设了330个测点,其中室内220个,室外110个,调查测量在秋季或春季进行,采样时间统一在上午8—10时。结果表明:全省居民室内外空气中~(222)Rn,的平均浓度分别为19.0和15.4Bq·m~(-3),~(222)Rn 子体α潜能的平均浓度分别为5.68×10~(-8)和4.67×10~(-8)J·m~(-3),~(220)Rn 的平均浓度分别为48.1和22.1Bq·m~(-3),~(220)Rn 子体α潜能的平均浓度分别为8.53×10~(-8)和3.81J·m~(-3)。全省居民吸入氡氧及其子体所致年有效剂量当量估计为1.31mSv,其中(气土)及其子体的贡献为0.40mSv。     

气体,水蒸汽和放射性核素对乳胶手套渗透性能的测定

本文分别用二种方法测定了用于操作放射性物质的三种材料(天然橡胶、氯丁和丁基橡胶)制成的乳胶手套薄膜的透气系数P_g、透气量Q_g、透湿系数P_v、透湿量Q_y和对~(210)Po等放射性核素的渗透系数。用真空压力法测得的三种材料四种气体(H_2、CO_2、O_2、N_2)的P_g值为(4.04×10~(-2)—3.66)×10~(-10)cm~2·s~(-1)·mmHg~(-1),Q_g值为(0.0249—2.18)×10~(-8)m~3·m~(-2)·d~(-1)·Pa~(-1);用重量法(透湿杯法)测得的三种材料五种型号手套薄膜的P_v值(0.157—2.23)×10~(-11)g·cm·cm~(-2)·s~(-1)·mmHg~(-1);Q_v值为0.30—20.3g·m~(-2)·d~(-1);用透湿杯法测得的对~(210)Po的渗透系数为1.42×10~(-2)—67.9mL·m~(-2)·d~(-1)。     

包头地区水体中天然放射性水平调查

本文报告了1984年包头地区水体中天然放射性核素浓度调查结果,黄河包头段的浓度范围分别是:U,13.8～80.5Bq·m~(-3);Th,0.30～1.72Bq·m~(-3);~(226)Ra,21.1～83.7Bq·m~3;~(40)K,99.6～114.1Bq·m~(-3)。其它水体中的浓度范围分别是:U,15.0～119.4Bq·m~(-3);Th,0.19～1.11Bqm~(-3);~(226)Ra,19.4～203.9Bqm~(-3);~(40)K,24.9～469.3Bqm~(-3)。     

制作校正用小型氡室

为了更方便校正氡测量仪,本文介绍日本东海大学工程系制作的小型氡室。用γ能谱法和比值法确定镭源氡释放率,在此基础上,计算出小型氡室的饱和氡浓度为(1.45±0.09)×10~5 Bq·m~(-3)。     

福岛核事故后上海气溶胶中~(131)I、~(134)Cs和~(137)Cs的来源途径分析

利用对气溶胶中典型放射性核素(~(131)I和134,~(137)Cs)的分析,可以评估福岛核事故产生的放射性物质对上海及全球的大气放射性本底水平造成的影响。本工作结合核事故释放过程、核素的天然衰变以及气象条件等因素,获得核事故期间上海的气溶胶中~(131)I和134,~(137)Cs活度浓度及其比值的分布特征:~(131)I被检出的时间(2011-03-27)早于~(134)Cs(2011-04-06)和~(137)Cs(2011-04-08),~(131)I的活度浓度(0.01~1.20 mBq/m3)比~(134)Cs(0.01~0.58mBq/m3)和~(137)Cs(0.01~0.65mBq/m3)大2~10倍,而且在不同的时间段出现相应的多峰值现象;~(131)I/~(137)Cs活度浓度比值(1.3~10.6)在2011年4月5日之后呈递减趋势,但是~(134)Cs/~(137)Cs活度浓度比值(0.8~2.9)则一直在1.1左右波动。利用HYSPLIT模型模拟放射性气团运移轨迹的分析方法,表明在核事故期间输入到上海的放射性气溶胶的途径有东北和西北两条主要迁移路径。同时通过结合国内相关城市核事故期间大气放射性监测数据,证实了东北路径在中国境内的控制地位。另外,通过总结和分析北半球大气监测数据中~(131)I/~(137)Cs和~(134)Cs/~(137)Cs活度浓度比值最大值的分布特征,验证了日本核事故产生的放射性气溶胶在北半球的传输过程。     

我国部分地区空气中氡及其子体α潜能浓度调查研究（1983—1990）

本文报道1983—1990年由国家环境保护局组织的我国部分地区空气中氡及其子体α潜能浓度调查(试点)的方法和初步结果。全国15省选择21个城市以及部分特殊地点(包括部分煤渣砖房、人防工程地下室、海滨、水面和溶洞等)开展了此项调查。调查采用瞬时测量(有双滤膜法、闪烁法、气球法、活性炭吸附解析法)和累积测量(固体经迹蚀刻法)两种方法。考虑到长时间的平均浓度对评价氡吸入危害更有意义,并注意到我国北方农村特殊居室——窑洞和某些高寒城市肺癌发病率可能较高的情况,在调查后期,还组织了专门力量,用固体经迹探测器 CSR,对延安窑洞和哈尔滨居民室内氡浓度进行了测量。调查中室外测点尽量与大气常规监测同位,室内测点注意选取不同的建筑物类型。调查结果表明:(1)这些城市室外平均氡浓度均值范围为(3.3-40.8)Bq·m~(-3)子体α潜能浓度均值范围为(1.54—11.4)×10~(-8)J·m~(-3);(2)室内平均氡浓度范围为(7.5—170.8)Bq·m~(-3),子体α潜能浓度均值范围为(3.0—45.5)×10~(-8)J·m~(-3);(3)在武汉东湖、浙江千岛湖和辽宁大伙房水库三个水面,氡浓度均值分别为4.63、5.50和2.2 Bq·m~(-3),氡子体的等效平衡氡浓度均值分别为3.20、3.62和0.88 Bq·m~(-3),氡子体对水面上方空气吸收剂量率的贡献,分别为1.0、1     

用CR-39核径迹探测器测量取自斯威士兰地下水中的氡浓度

几项研究表明,位于水中的~(222)Rn会对室内空气产生影响。一种被动式氡测量方法可用于确定斯威士兰井中地下水的氡活度浓度。对一个有代表性的井进行了为期一年的观测,其氡浓度在1.8±0.1Bq·L~(-1)～152.9±4.8Bq·L~(-1)之间。在这个范围内只有轻微的变化(离平均值的最大偏差为2.4σ)。在地下水源中测定的~(222)Rn浓度的算术平均值是25.2Bq·L~(-1),几何平均值则是13.5Bq·L~(-1)。有54％的井中水的~(222)Rn浓度超过了美国环境保护机构对公共饮用水源建议的11Bq·L~(-1)的极限。     

异形探头表面沾污仪的研制

本工作研制了具有特殊形状的表面沾污监测仪,探头方向可改变,并可拉伸,能用于监测管道内部,容器内部或其它不规则表面的沾污.探头采用J418型不锈钢云母端窗计数管,有效窗口为φ15mm和面积为70×70mm两种,端窗上复盖一层0.98mg·cm~(-2)厚的铝化聚脂膜.探头拉杆长度可从20cm伸长到100cm.该监测仪小探头(φ15)的表面活度响应对~(90)Sr+~(90)Y,~(204)Ti,~(147)Pm和~(241)Am源分别为0.55、0.47、0.14和0.19CPS/Bq·cm~(-2);测量时间10秒时,最小可探测限分别为0.32,0.39,1.60和0.42Bq·cm~(-2),满足退役设备去污监测的要求.     

广州市区室内外空气中氡及其子体浓度调查

本文报道了1984年7月至1985年2月间对广州市区住宅室内外空气中氡(气土)及其子体浓度的初步调查。结果表明:室内外空气中平均~(222)Rn 浓度分别为17.8和13.3Bq·m~(-3),平均~(222)Rn 子体浓度(平衡当量浓度)分别为10.6和8.8Bq·m~(-3);平均~(220)Rn 浓度分别为37.0和14.5Bq·m~(-3),平均~(220)Rn 子体浓度(平衡当量浓度)分别为0.92和0.62Bq·m~(-3)。市区居民吸入氡(气土)及其子体所受的有效剂量当量估计为1.29mSv,与 UN-SCEAR 估计的全球温带地区水平相近,其中(气土)及其子体的贡献为0.35mSv,约为全球正常本底地区的2倍。     

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.     

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.     

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.