冠醚萃取法分离铀同位素的研究

本文研究了二环已基24冠8(DCH24C8)和二环已基18冠6(DCH18C6)的1,2-二氯乙烷溶剂萃取铀(VI)和铀(IV)的同位素效应,通过多级富集和贫化级联测定了铀同位素的平均单级分离因子,证实了在不变价态铀同位素分离体系中,冠醚体系的铀同位素效应显著大于其它体系。     

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)。     

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。     

锂盐-冠醚络合物化学交换体系中的同位素效应

对8种锂盐-冠醚络合物的两相体系进行化学交换并确定了平衡单级分离系数。证实了同位素效应与两相化合物种的键强差有很大关系,揭示了影响分离系数的因素。找到了一种迄今尚未公开发表的4甲基-苯并-15-冠-5体系,其萃取分离锂同位素的单级分离系数达到了1.035—1.047。环己基-15-冠-5体系单级分离系数为1.035。在没有价态变化的条件下进行~6Li的浓集。所有情况,~6Li均浓集在有机相中。采用一种新的大有机阴离子——三氯乙酸根作为对离子进行萃取,代替Jepson使用过的三氟乙酸(HTFA)。研究了溶剂对分离系数的影响,采用介电常数稍高的1.2-二氯乙烷为溶剂,物化性能好、两相比重适宜,有利于同位素分离。在实验的基础上,探讨了结构与性能之间的内在联系。表明,大环效应是显著的。展示了锂盐-冠醚络合物化学交换体系萃取分离锂同位素的前景是乐观的。进一步为发现新的体系,探讨工艺应用可能性,提供依据。     

~(235)U/~(231)Pa质谱法测铀年龄

建立了同位素稀释-多接收电感耦合等离子体质谱法测~(235)U/~(231)Pa原子比得到高浓铀年龄的方法。经过两次TTA萃取-反萃后从母体237 Np中分离得到233Pa稀释剂,Pa中去Np的去污因子均在200以上。在用标准物质CRM U900对233Pa稀释剂的浓度进行标定后,分别以233 U、233 Pa作为~(235)U、231 Pa的稀释剂,质谱测得~(235)U/~(231)Pa原子比计算高浓铀年龄,采用该法对标准物质CRM U850进行年龄测量,其结果与参考值的相对偏差为1.97%。该法可用于核法证与核保障监督中的高浓铀年龄测定。     

U（Ⅳ）,U（Ⅵ）在萃取分离过程中的同位素交换

一、引言近年来不同价态之间铀同位素交换速度的研究,越来越引起人们的重视。其原因是铀同位素交换速度的快慢,直接关系到铀同位素分离的成败,因而研究铀同位素交换速度,是一个很重要的问题。通过实验发现U(Ⅳ),U(Ⅵ)在萃取分离的瞬间,有同位素交换现象,尤其在Fe~(2 )的     

研究动态

中国原子能科学研究院放射化学所同位素分离组在离子交换色谱法分离铀同位素的基础研究方面最近取得突破性进展。该研究组采用的一个分离体系,是使原料铀溶液在2.5h内通过约1m长的色层柱,在后沿界面上得到了丰度R=[~(235)U]/[~(238)U]=0.008180的浓缩样品,比料液(天然铀)丰度0.007280提高12％以上。日本在离子交换色谱法分离铀同位素这一     

同位素稀释质谱法测定高放废液中的铀

用双同位素稀释质谱法测定高放废液中的微量铀,采用TBP/Kel-F粉反相分配色层法分离铀,双稀释剂分别为浓缩~(235)U及~(238)U,铀同位素丰度比的质谱测定相对标准误差优于0.1%,化学处理及质谱测定全流程铀的空白值为3×10~(-9)g,方法检测限对于铀为1×10~(-9)g,高放废液中微量铀测定结果不确定度为±2%。     

用中子活化分析法测定~(238)U/~(235)U同位素丰度比

本文论述了用中子活化分析法测定含微量铀的样品中~(238)U/~(235)U同位素丰度比的原理及方法。样品在反应堆中接受短时间照射后,用Ge(Li)探头或高纯锗探头-多道能谱分析仪-计算机系统测量射线的能谱.可以分辨出~(238)U和~(235)U的许多监测峰。利用这两种监测峰计数之比与这两种同位素丰度比成正比的关系,分析铀的同位素丰度比,在~(235)U丰度为0.6％-18％范围时精密度为1％-2％,在贫化铀和18％-60％丰度~(235)U时,精密度为2％-3％。     

用二(2—乙基己基)磷酸从不同混合物介质中萃取分离铀、钍和铈

用二(2-乙基己基)磷酸(HDEHP)系统地研究了纯盐酸和硫酸溶液以及它们的混合溶液中,U(Ⅵ)、Th(Ⅳ)和Ce(Ⅲ)的萃取。同时还研究了可混溶于水的醇类和丙酮对萃取铀、钍、铈的影响。讨论了研究结果,并推荐了U(Ⅵ)、Th(Ⅳ)、Ce(Ⅲ)的分离方法。根据所得结果提出了可能的萃取机理。     

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.