TRPO 萃取-固体荧光法测定土壤和空气尘埃中的铀

本文介绍了用 TRPO 萃取-固体荧光法测定土壤和空气尘埃中铀的方法。用混合铵盐和硫酸-硝酸分别预处理土壤和空气尘埃样品,在硝酸体系中用30%TRPO 的 OK 溶液萃取铀,制备 NaF 熔珠,测定铀含量。实验结果表明,本方法对土壤和空气尘埃样品中铀的全程回收率分别为(89.6±11.8)%和(85.5±5.6)%,灵敏度分别为0.03μg/g 和0.2pg/L。     

TRPO萃取荧光法测定尿和水中铀

近年来,国内多采用磷酸三丁脂、乙酸乙酯~([1])和三辛基氧膦(TOPO)萃取法~([2])。及激光荧光法~([3])测定尿和水中铀。文献[4]较全面地介绍了铀的荧光法测定。文献[5]报道了使用三烷基(混合)氧膦(TRPO)代替TOPO萃取和Br-PADAP分光光度法测定矿石、矿渣中的微量铀,取得了与TOPO同样的分离效果。文献[6]较详细地研究了用TRPO从高放废水中萃取U、Np、Pu、Am、Cm、Pm和Tc,探讨了用这种方法处理超铀废水的可能性。TRPO为磷肥厂产品,较TOPO价廉易得。     

TRPO—PVF2萃取色层分离,5—Br—PADAP光度法测定金属样品中微量铀

本文对 TRPO(三烷基混合氮膦)-PVF_2(聚偏氟乙烯)萃取色层分离,5-Br-P ADAP光度测定微量铀的方法进行了较系统的研究;并应用此方法分析了铀污染的钢铁、铝、铜、镍等金属物件中的微量铀。该方法操作简单,快速,能去除大量基体金属离子的干扰。该方法的最小检测限为1μgU/g 金属样品。精密度为±5％,铀的回收率大于95％,可满足金属样品中微量铀的分析要求。     

TRPO-TBP/煤油体系对高放废液中镅、铀、钚和锝等的萃取和反萃

比较研究了混合三烷基氧膦（TRPO）－磷酸三丁酯（TBP）／煤油混合体系和TRPO／煤油体系对铀和硝酸的萃取含量,结果表明,混合体系的萃取容量比TRPO／煤油体系高。测定了20％TRPO－20％TBP／煤油混合体系对二十余种离子的萃取分配比,结果表明在较宽的NHO3浓度范围（0.5-5mol/L)内,该混合体系对低浓度UO2^2 、低浓度U^4 ,Pu^4 ,Pu^3 ,NpO2^2 ,Np^4 都有较高的萃取能力;低酸条件（＜1.0mol/L)下,混合体系对TcO4^-1,Am^3 ,Eu^3 ,Y^3 有较高的分配比;混合体系对NpO2^ ,Sr^2 ,Cs^ 等的萃取能力较弱。TRPO－TBP／煤油有机相中萃取的镅、铀、钚和锝可以分别用高浓度硝酸、碳权铵溶液、羟基乙酸和高浓度硝酸（或碳酸盐）反萃下来。     

P-350萃取色层法测定食品中微量钍

文献[1,2]曾报道了以国产胺类萃取剂 N-235为固定相的萃取色层分离法测定食品及天然水中微量铀、钍、镭。本文提出以中性膦类萃取剂甲基膦酸二甲庚脂(简称 P-350)作为固定相的萃取色层法,测定食品中微量钍。实验表明 P-350对铀、钍有良好的萃取选择性,并且由于其水溶性较小,而更适宜于作为萃取色层中的固定相。食品灰样经酸溶液浸取后,在2M HNO_3介质中流经色层柱,除去大部分杂质,然后以6M HCl 淋洗钍,即可用偶氮胂 III 比色测定。本方法简便,回收率高,选择性好。     

季铵萃取树脂色谱分离-ICP/AES法测定核纯级二氧化铀中7种杂质元素的研究

选萃了237季铵萃取树脂,利用萃取色谱分离技术,使铀与待测杂质元素在6.5mol/L HNO_3介质中得到定量分离。用975型ICP直读光谱仪同时测定核纯级二氧化铀中Ba、Be、Nb、Ru、Sb、Sn和Ta,测定下限为0.013μg/g～0.50μg/g,回收率为98％～103％,相对标准偏差<5％。     

N—235萃取色层法分离和测定钚

提出了用N-235/聚四氟乙烯柱萃取色层法从铀、镎和镅中分离钚的方法:从2.0mol·l~1 HNO_3溶液中吸附钚,用1.0mol·l~1 HNO_3溶液洗涤,再用HNO_3-H_2C_2O_4溶液洗脱。钚的回收率为97.4±1.8%。     

γ辐射对30%TRPO-煤油萃取性能及物理参数的影响

测试了γ辐照剂量对国产三烷基氧膦(TRPO)萃取性能、反萃性能(U、Pu、Am、En、Pm)、物性参数(密度、粘度、折光率、紫外透光率)的影响。用红外光谱观察了辐解产物的特征峰,检出了聚合物、烷基膦酶、亚硝基化合物、硝基化合物、羰基化物等辐解产物,用简单的5%Na_2CO_3-1mol/L HNO_3-H_2O洗涤法,可把主要的辐解产物除去。研究结果表明:TRPO具有良好的辐照稳定性,可以安全地用于处理强放废液和某些超铀靶件。     

阴离子交换分离控制电位库仑法测定辐照后核燃料元件溶解液中的钚

本文提供了一个阴离子交换分离,控制电位库仑法测定辐照后核燃料元件溶解液大量铀中小量钚的方法。钚(Ⅳ)在7.5 NNO_3介质中吸附在711型树脂床上,用7.5N HNO_3洗涤铀、裂变产物和其它杂质元素后,用0.5N HNO_3-0.02M NH_2OH·HCI洗涤钚,最后以1 NHN0_3为支持电解质,金丝网作工作电极进行库仑测定。测定范围为1—4 mg钚。用化学校正方法,对辐照后核燃料元件溶解液样品7次平行测定的相对标准偏差为±0.33%。     

萃取色层分离-水平式ICP/AES法测定U_3O_8中25种杂质元素

文章叙述了用TBP萃取色层法分离,水平式ICP/AES法测定U_3O_8中25种杂质元素的分析方法。样品转化为硝酸铀酰后,采用以CL-TBP萃淋树脂为固定相,5mol/l HNO_3为流动相的萃取色层法使杂质元素与铀基体分离,杂质流出液以水平式ICP为激发光源的发射光谱分析法直接测定,取样0.3g,所有元素的测定下限在0.01×10~(-6)～5×10~(-6)之间,方法的重加回收率在82%～121%之间,相对标准偏差在13%以内。     

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.