冠醚萃取氯化铀酰的研究

研究了五种冠醚的1,2-二氯乙烷溶液从盐酸水溶液中萃取铀(VI)的行为。实验表明,铀(VI)分配比与水相盐酸浓度、LiCl浓度、有机相冠醚浓度有关。用斜率法和等摩尔系列法确定了18-冠-6、二苯并-18-冠-6、二苯并-24-冠-8、二环己基-18-冠-6、二环己基-24-冠-8与铀(VI)萃合物的组成比,并求得它们的萃取平衡常数。     

无载体~(18)F的制备及快速标记

研究了以苯并-12-冠-4、15-冠-5、18-冠-6、二苯并-24-冠-8的锂络合物为靶子,在反应堆内照射,通过~6Li(n,t)~4He,~(16)O(t,n)~(18)F二次核反应制备无载体~(18)F,并以靶子物冠醚为溶剂直接进行了~(18)F的快速标记。由于~(18)F~-的“裸露”离子效应,加速了~(18)F~-与CH_2Br(CH_2)_(14)CH_3化合物中Br~-之间的交换,标记率>90％,产额80±5％。本方法把~(18)F的制备、分离和标记统一起来,操作时间较短,适合于短半衰期~(18)F快速标记的需要。     

高分子冠状聚合物对痕量铀(Ⅵ)的选择性吸附及其在分离中的应用

近年来,高分子冠醚的出现引起了人们的广泛兴趣。S.Kopolow首先合成乙烯基苯并-15-冠-5及苯并-18-冠-6的高聚物。W.H.Teigenbaum,J.M.Lehn分别合成了聚胺和主链含胺冠醚。E.Blasius还报道了酚醛型二苯并-18-冠-6和二苯并-24-冠-     

冠醚萃取同位素砹-211

为深入了解砹的化学性质,探索用冠醚作相转移催化剂来标记砹的化合物的可能性,采用冠醚二环己基-18-冠-6(DC18C6)于各种溶液中进行砹的萃取研究。 盐酸浓度变化显著影响DC18C6对~(211)At的萃取。随HCl浓度增加,萃取率急剧上升,在2mol·l~(-1)HCl时,萃取率可达99％。而用异丙醚萃取At需在8mol·l~(-1)HCl下进行,在2mol·l~(-1)     

二苯并-18-冠-6对某些放射性核素的萃取与萃取色层分离

本文研究了二苯并-18-冠-6对~(22)Na、~(45)Ca、~(86)Rb、~(90)Sr-~(90)Y、~(137)Cs和~(144)Ce等放射性核素的萃取和萃取色层分离。冠醚萃取金属离子具有离子对萃取的特征,据此,选择苦味酸根离子为反离子,以三氯甲烷为溶剂。 测定了30℃时Na~+、Rb~+、Cs~+、Ca~(2+)、Sr~(2+)和Ce~(3+)的萃取平衡常数(K_(ex))。对单价和二价金属离子,K_(ex)次序分另0为;Rb~+>Cs~+>Ns~+和Sr~(2+)>Ca~(2+)。 使用二苯并-18-冠-6的萃取色层有效地分离了~(22)Na-~(137)Cs、~(45)Ca-~(90)Sr和~(144)Ce-~(90)Sr-~(90)Y。     

冠醚与铀酰盐、钍盐络合物的红外光谱研究

本文指出,对18-冠-6,苯并-15-冠-5和二苯并-18-冠-6及其与硝酸铀酰、钍盐络合物用KBr压片制样,不能得到真实的红外光谱,用石蜡油制样则可获得真实的红外光谱。文中报道了冠醚与铀酰盐、钍盐形成络合物后,特征基团吸收频率的位移情况,并且解释了文献中用KBr压片制得的光谱简化且相似的原因,讨论了冠醚的硝酸铀酰、钍盐络合物用KBr压片制样时在1380cm~(-1)处出现吸收峰的问题。此外,在冠醚的硝酸铀酰、钍盐络合物中,对1500—1560cm~(-1)范围内的吸收峰的归属,我们的见解与文献中的观点不同。     

冠醚萃取铀、钚、镅和铈的研究

本工作研究了二苯并—18—冠—6(DB 18 C 6)从硝酸介质中萃取铀、钚等元素的行为。纯硝酸溶液中萃取铀、钚的分配比很小,但当水相存在硝酸盐(例如NH_4NO_3)时,由于盐析效应,Pu(Ⅳ)、U(Ⅳ)和U(Ⅵ)的分配比均有很大增加。本文较系统地研究了DB 18 C 6作萃取剂时,水相酸度、DB 18 C6浓度、盐的种类及浓度对萃取的影响;求得在Pu的萃合物中溶剂化数为2。此外还比较了几种冠醚的萃取行为,发现苯并和其它二苯并冠醚对铀、钚、镅的萃取行为类似于DE 18 C6,也有盐析效应,二环已基—18—冠—6能从纯硝酸溶液中很好地萃取铀和钚。     

用4-叔丁基苯并-15-冠-5及4-溴苯并-15-冠-5萃取镧系元素

本文研究了 4-叔丁基苯并-15-冠-5(t-BBC)和4-溴苯并-15-冠-5(BrBC)的硝基苯溶液对七个镧系元素的萃取(苦味酸根为伴随离子),其萃取分配比次序为CeEu>Tm>Yb>Lu;计算了平均分离因数。萃合物的组成可能是Ln(t-BBC)_2Pi_3。以氯仿作稀释剂时分配比很低。以BrBC代替t-BBC作萃取剂时分配比约低一倍。     

冠醚萃取钍(Ⅳ)的化学平衡及其萃合物的红外光谱

本文研究了数种冠醚的1,2-二氯乙烷溶液从硝酸、盐酸和苦味酸等水溶液中萃取钍的行为。在硝酸介质中,钍与二环己基-18-冠-6(DC18C6)或二环己基-24-冠-8(DC24C8)形成了萃合物Th(NO_3)_4·2L·HNO_3(L为冠醚)。其相应的萃取平衡常数(25℃)经测定分别为:K_(DC18C6)=3.98和K_(DC24C8)=6.30。 测定了萃合物Th(NO_3)_4·2DC18C6·HNO_3和Th(NO_3)_4·2DC24C8·HNO_3的红外光谱。差示光谱的特征吸收峰表明,金属离子和冠醚环上氧配位原子之间可能存在直接的键合,以及萃合物中NO_3根参与配位。     

二苯并-18-冠-6从盐酸溶液中萃取铀(Ⅳ)和铀(Ⅵ)

二苯并-18-冠-6-硝基苯,从高浓度的盐酸或氯化物溶液中,能有效地萃取铀(Ⅳ)和铀(Ⅵ)。不同碱金属阳离子对萃取的影响,符合冠醚与阳离子络合作用的顺序:K~ >Na~ >Li~ ,少量钾离子的引入能显著提高对铀的萃取效果。通过对有机相中铀性质的研究和固体萃合物的成份分析,指出在被萃取的离子对中铀(Ⅳ)和铀(Ⅵ)是以氯络阴离子[UCl_6]~(2-)、[UO_2Cl_4)~(2-)的形式存在。采用饱和萃取法和等克分子系列法,确定了在盐酸体系中萃合物的组成为:H_2UCl_6·2DBC、H_2UO_2Cl_4·2DBC。当有与冠醚络合作用强的阳离子存在时,萃合物中的氢将被该阳离子所取代。     

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.