硝酸介质中二环己基18-冠-6对锶的萃取

利用冠醚二环己基-18-冠-6（DCH18C6）作为萃取剂在硝酸介质中对锶的萃取性能进行了系统研究,考察了稀释剂、硝酸浓度、振荡时间、温度对锶萃取的影响,结果表明,该萃取体系与硝酸的浓度有关,当萃取剂浓度为0.01mol/L,以1,1,2,2-四氯乙烷为稀释剂,硝酸浓度为1mol/L时,锶的萃取率可高达92%左右,利用纯水作为反萃剂,反萃率可达(99.56±1.7)%左右。该萃取反应动力学比较快,可在10min 达到平衡,热力学实验表明该萃取反应是一个放热反应。同时选择性萃取实验结果表明,冠醚二环己基-18-冠-6能有效地从多种离子共存的体系中选择性地萃取锶。     

二环己基-18-冠-6萃取铀、钚和镅的研究

本文叙述了溶剂种类、酸度和冠醚浓度诸因素对二环己基18冠6(DCH 18 C 6)萃取铀、钚等元素的影响,着重研究了常量铀的萃取行为。结果表明,1,1,2—三氯乙烷作溶剂时,DCH18 C 6对微量铀或常量铀均能萃取。在硝酸体系形成的萃合物中,Pu(Ⅳ)和U(Ⅵ)与二环己基18冠6的分子比分别为2和1。DCH 18 C 6-1,1,2—三氯乙烷能够从含有U(Ⅵ)和U(Ⅳ)的3—5 M HCl溶液中单独萃取U(Ⅵ)而不萃取U(Ⅳ)。     

二环己基18冠醚-6/异丙氧基杯[4]冠-6-正辛醇共萃取Sr和Cs

以正辛醇作稀释剂,二环己基18冠醚-6(DCH18C-6)和异丙氧基杯[4]冠-6(IPR-C[4]C-6)作为萃取剂进行了从硝酸介质中共萃取分离Sr和Cs的研究.研究了萃取剂浓度、硝酸浓度、温度等因素对Sr, Cs的萃取性能影响.研究结果表明,2种萃取剂相互之间没有明显的协萃作用,分别独立进行对Sr和Cs的萃取.通过选择合适的萃取和反萃条件可以满足体系对Sr, Cs的萃取和反萃要求.     

N，N′-二甲基-N，N′-二辛基-3-氧杂-戊二酰胺对Np(Ⅳ，Ⅴ，Ⅵ)的萃取行为

²³⁷Np半衰期较长,具有较高的生物毒性,使其成为高放废液非α化过程中重点关注的核素之一。本工作采用新型的N,N′-二甲基-N,N′-二辛基-3-氧杂-戊二酰胺(DMDODGA)为萃取剂,研究了萃取剂浓度、水相初始硝酸浓度和温度等因素对DMDODGA萃取Np(Ⅳ)、Np(Ⅴ)、Np(Ⅵ)的影响。结果表明：随着DMDODGA浓度和水相初始硝酸浓度的增加,Np(Ⅳ)、Np(Ⅴ)、Np(Ⅵ)的分配比均增大。萃取剂浓度小于0.005 mol/L时,DMDODGA与Np(Ⅳ)生成1∶2型萃合物;萃取剂浓度大于0.005 mol/L时,DMDODGA与Np(Ⅳ)生成1∶3型萃合物。萃取剂浓度在0.1~1.0 mol/L范围内,DMDODGA与Np(Ⅴ)、Np(Ⅵ)均生成1∶2型萃合物。DMDODGA萃取Np(Ⅳ)、Np(Ⅴ)、Np(Ⅵ)的ΔH分别为-59.55、-22.02、-31.40 kJ/mol,3个反应均为放热反应,降低温度有利于反应的正向进行。     

四种二环己基系列的冠醚对UO_2(NO_3)_2的萃取

本工作研究了十五种不同结构的冠醚在硝酸介质中对UO_2(NO_3)_2的革取。结果表明:二环已基系列的冠醚对UO_2(NO_3)_2络合萃取的性能较其他冠醚为好,其中以二环己基—24冠—8和二环己基—27—冠—9对UO_2(NO_3)_2的萃取性能最好。还研究了水相酸度、平衡时间、反萃性能及铀浓度等因素对萃取的影响。经实验测定:二环己基—30—冠—10、二环己基—27—冠—9、二环己基—24—冠—8和二环己基—21—冠—7与UO_2(NO_3)_2所形成的萃合物组成比皆为1:1。所计算出的萃取平衡常数分别为:K_(DCH18C?)=11.5;K_(DCH21C7)=11.2;K_(DCH24C?)=18.2;K_(DCH27C?)=14.2;K_(DCH30C10)=12.9。     

锕系、镧系元素分离中新萃取剂的研究(Ⅴ)--HCBMPPT和TBP对铀的协同萃取

本文研究了4-邻氯苯甲酰基-2,4-二氢-5-甲基-2-苯基-3H-吡唑硫酮-3(HCBMPPT)与中性萃取剂磷酸三丁酯(TBP)的甲苯溶液从硝酸介质中对铀(Ⅵ)的协同萃取.实验结果表明,其萃取分配比随萃取剂浓度、协萃剂浓度、盐析剂浓度及pH值的升高而增大.同时,对萃合物的化学组成及萃取机理进行了分析和讨论.     

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。     

2,6-双(5,6-二异丙基-1,2,4-三唑-3)吡啶对镅和铕的萃取

为了解2,6-双(5,6-二异丙基-1,2,4-三唑-3)吡啶（iPr-BTP）在硝酸介质中对镅和铕的萃取行为，以30%辛醇/正十二烷溶液为稀释剂，考察了稀释剂的组成、萃取时间、硝酸浓度、萃取剂浓度及硝酸钠浓度对iPr-BTP萃取Am(Ⅲ)和Eu(Ⅲ)的影响，确定了萃合物组成和萃取反应方程式。实验结果表明，该萃取剂对镅的萃取能力较强，而对铕的萃取能力较弱。iPr-BTP对Am(Ⅲ)和Eu(Ⅲ)的萃取反应方程式可表示为： M³⁺+3NO^-₃+3(iPr-BTP)_(o)→M(NO₃)₃·3(iPr-BTP)_(o)。     

N,N''''-四己基丙二酰胺-正辛烷溶液从硝酸介质中萃取铀

研究了新萃取剂N,N'-四己基丙二酰胺-正辛烷溶液从硝酸介质中萃取铀的机理.考察了水相硝酸浓度、萃取剂浓度、硝酸钠浓度以及温度对萃取分配比的影响,确定了萃合物的组成.借助红外光谱分析了萃合物的结构.求得了萃取硝酸铀酰的平衡常数及反应的热力学函数.与四丁基丙二酰胺相比减少了三相生成的倾向.同时研究了稀释剂的影响,发现该萃取剂在正辛烷中比在甲苯中萃取能力强,并对上述结果进行了解释.     

N-吡咯烷基-2-吡啶甲酰胺与1，10-菲啰啉对U（Ⅵ）的协同萃取

研究了N-吡咯烷基-2-吡啶甲酰胺(NPPFA)与1, 10-菲啰啉(1, 10-phenanthroline, phen)在硝酸介质中对U(Ⅵ)的协同萃取行为.以二氯乙烷为稀释剂,考察了NPPFA的摩尔分数、水相pH值、盐析剂浓度及温度对萃取分配比的影响.结果表明,NPPFA与phen有显著的协萃作用;当pH大于2.2时,萃取体系易发生乳化现象;盐析剂的加入可以大大提高萃取效率.并用斜率法确定了萃合物的组成为UO2(NO3)2·NPPFA·phen.     

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.