UO_2~(2+)-吡咤-3-甲酸-乙基紫离子缔合物高灵敏显色反应的研究

本文用萃取光度法研究了UO_2~(2+)-吡啶-3-甲酸-乙基紫离子缔合体系的显色反应,提出了用苯:MIBK(3:1)作为萃取剂的一个高灵敏度的显色休系,探讨了萃取比色的最佳条件,并进行了合成试样中铀的测定。     

偶氮氯磷Ⅲ双波长分光光度法同时测定铀矿石中钍和铀

对偶氮氯膦Ⅲ和钍、铀在磷酸体系中的显色行为作了研究,提出以TRPO-G.D.X-301萃取色层分离稀土、钛、锆等干扰元素、用双波长分光度法同时测定铀矿石中钍和铀的方法。测定钍和铀时,测量波长、参比波长分别为690nm、608nm和670nm、707nm,工作曲线在0～50μg/25ml内成线性。测定矿石中0.03%～0.5%的钍和铀时,误差小于10%。本法可用于复杂样品中钍和铀的同时测定。     

在表面活性剂存在下钍与2,3,4—三羟基—4‘—磺酸偶氮苯显色反应的研究

变色酸偶氮类显色剂是目前光度法测定钍的主要试剂。这类试剂的特点是灵敏度高,稳定性好,但不足的是希土、铀的干扰严重,测定范围较窄。本文研究了在阳离子表面活性剂氯化十四烷基吡啶(TPC)存在下,钍与2,3,4-三羟基-4’-磺酸偶氮苯(TSAB)的显色反应条件。三元络合物的形成提高了分析方法的灵敏度,其表观摩尔吸光系数ε_(460)=4.95×10~4,较文献中报道的二元络合物提高了二倍。该法能在1000倍希土和40倍铀存在下光度法测定钍。     

用六偏磷酸钠校核反应快速光度测定微量钍

目前,对大于10~(-7)克的微量钍普遍采用钍与偶氮砷Ⅲ(又名铀试剂Ⅲ)产生蓝绿色的颜色反应进行分光光度测定。其中绝大部分方法都是在测量消光值后从工作曲线上查得相应的钍含量。由于偶氮砷Ⅲ是极为灵敏的显色试剂,它与钍、铀、锆、稀土、钼、钛、铁、     

萃取-比色法测定热铀溶液中的微量锆

本文研究了在HNO_3介质中使用0.01 M PMBP-氯代苯/二甲苯萃取分离锆的条件以及Zr-0.01 M PMBP有机相直接使用0.05%二甲酚橙-乙醇(95%)显色的条件,确定了比色测定含有铝、铁、钚、镎、钍和氟等离子的热铀溶液中微量锆的分析程序。此程序对锆萃取分离的选择性较好,比色操作简便。     

分光光度法测定高放废液中的稀土总量

采用冠醚-杯冠-正辛醇萃取剂在适宜酸度条件下萃取高放废液中的锶、铯,萃余水相调节酸度后,用三正辛基氧化磷(TOPO)-环己烷将铀、钚、钍等萃入有机相,萃余水相在一定酸度条件下,可以采用偶氮氯膦mA与稀土元素直接显色,进而采用分光光度法测定其稀土总量。对冠醚-杯冠-正辛醇萃取剂萃取高放废液中的⁹⁰Sr和¹³⁷Cs进行了条件实验,确定了TOPO萃取不影响稀土元素测定的实验条件,对偶氮氯膦mA显色测定稀土元素的显色条件进行了研究,最终建立了此分析方法。结果表明,在4.5 mol/L硝酸体系中,冠醚-杯冠-正辛醇萃取剂可以萃取高放废液中的⁹⁰Sr和¹³⁷Cs,而不影响稀土元素的测定。在0～10 mg/L范围、670 nm处,偶氮氯膦mA与稀土元素显色,吸光度与稀土元素的质量呈线性关系。采用此方法测定模拟高放废液中总稀土含量,相对标准偏差为2.3%(n=6),重加回收率为89.9%～97.7%;真实高放废液中稀土元素总量测定的相对标准偏差为6.3%(n=3)。     

用2-羟基-1-萘醛异菸酸腙分光光度法测定共存的铀(Ⅵ)和钍(Ⅳ)

铀(VI)和钍(IV)在微酸性介质中与2-羟基-1-萘醛异菸酸腙(2-HNIH)反应,分别生成黄色和橙色的络合物。只有铀(VI)的络合物能被萃取入异戊醇,当铀,钍同时存在时,用此分光光度法同时测定铀(VI)和钍(IV).     

用氯化甲基三辛胺和二甲酚橙萃取-分光光度法测定钍

元素的直接萃取-分光光度法的优点是速度加快和灵敏度增加,可以用来解决一些特殊的分析任务。在以前的工作中,曾用一种对钍的溶解性能强和选择性的溶剂(季铵盐Aliquat-336)分离钍,并接着在水反萃取液中测定钍。由于二甲酚橙已成功地应用于正辛胺溶液中比色测定锆,现在又将它进一步用于在Aliquat-336溶液中测定钍。     

用3-亚硝基-4-羟基香豆素分光光度测定钍(Ⅳ)

导言自从钍的分析化学专著和分析化学大全出版以来,大批的有机试剂被建议用于钍的比色测定,其中绝大部分试剂可用于ppm级钍的测定。但是,外来离子,尤其是钛(Ⅳ)、     

二异丁基甲酮萃取分离-电感耦合等离子体原子发射光谱法测定磷灰石矿中的铀和钍

用溶剂萃取分离电感耦合等离子体原子发射光谱法验证了磷矿石中锕系元素(铀和钍)的测定。对铀和钍来说,由于磷灰石中钙的光谱干扰和由主要组分(磷酸钙)产生的负干扰同时出现,因此,在磷灰石矿用热硝酸处理后,需用溶剂萃取法将铀和钍从磷酸钙中分离出去。在本研究中,用1-苯基-3-甲基-4-三氟乙酰-5-吡唑啉酮(HPMTFP,pK_a=2.56)作为萃取试剂,选择二异丁基甲酮(DIBK)作为萃取有机溶剂。当pH值超过2时,铀和钍被定量萃取,并能从磷灰石组分中分离出来,有机相直接在ICP-AES光谱仪上测定。 利用该方法测定了美国佛罗里达磷灰石矿中的铀和钍含量,U(103±2.2)×10~(-6)和Th(8.84±0.19)×10~(-6)。这些结果与利用ICP-MS测量得出的结果相吻合。     

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.