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3-苯基-4-苯甲酰-5-异噁唑酮在二异丁酮中溶剂萃取分离电感耦合等离子体发射光谱法测定磷灰石矿物中的铀

本文用溶剂萃取电感耦合等离子体发射光谱法(ICP-AES)测定磷灰石矿物中的铀。使用3-苯基-4-苯甲酰基-5-异噁唑酮(HPBI)高酸度萃取剂(pK_A=1.23)和二异丁酮(DIBK)能使铀从很低pH范围内萃取出来,并与干扰元素分离,而且避免了磷酸钙的沉淀,磷灰石矿物用浓硝酸处理。在除去少量不溶性残渣之后,用0.06mol HPBL将铀萃入DIBK(pH0.3),以分离干扰元素。用ICP-AES测定铀,并直接注入DIBK相。选定波长367.01nm,得到最高的强度比,即在DIBK相中铀的发射强度对背景的比,和最好的检测限(0.02mg/L)。测得在磷灰石中铀的含量是(1.06±0.12)×10~(-2)%。     

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。     

萃取和分光光度法测定矿石中的铀

为了测定矿石中痕量铀,提出了一个萃取分光光度测定方法。此法是用三辛基氧膦甲苯溶液萃取铀,并在有机相中不经反萃取藉助NN-二甲基甲酰胺用乙二醛双(2-羟基缩苯胺)(GBH)或1-(2-吡啶偶氮)-2-萘酚(PAN)显色。用GBH作显色剂时最大吸光度出现在波长600nm处,克分子吸光系数为1.48(±0.01)×10~4 1mol~~(-1)cm~(-1),用PAN作显色剂时,最大吸光度出现在波长555nm处,克分子吸光系数为2.61(±0.02)×10~41mol~(-1)cm~(-1)。用GBH作显色剂,波长选在600 nm,铀(Ⅵ)含量在0.6—10.5μgml~(-1)(对应的样品中铀量为20—350μg)范围内符合比尔定律。用PAN作显色剂,波长选在555nm,在铀(Ⅵ)含量0.3—6.0μgml~(-1)(对应的样品中铀量为10—200μg)范围内符合比尔定律。     

铀化合物中微量钽的萃取色层分离—ICP／AES测定

以CL-TBP萃取色层分离-水平式ICP/AES测定铀化合物中微量Ta。方法是先将铀化合物转化成硝酸铀酰,再以含0.2mol·l ?HF的3mol·l~(-1)HNO_3溶液溶解微量Ta,然后进行分离和测定。取样0.3g,测定下限为0.5×10~(-6);当Ta含量为1.7×10~(-6)-5.0×10~(-6)时,方法的加入回收率在88%106%范围内;相对标准偏差≤10%。     

用三异辛胺萃取法联合测定废水中的铀和钚

本实验研究了用三异辛胺(TIOA)萃取分离铀(VI)和钚(IV)的条件,并在此基础上拟定了废水铀钚联合测定方法。用 TIOA-二甲苯从盐酸中提取铀(VI)和钚(IV),用硝酸反萃铀,加偶氮氯磷 III(CPAIII)后进行分光光度测定,比尔定律范围0—10微克/10毫升,回收率近100%,50微克/升时精密度为4%(9次);钚用草酸-硝酸混合液反萃,α计数法测定,浓度为2.5×10~(-11)—2.7×10~(-9)居里/升时,34次平均回收率为87.4%,精密度优于11%。方法简便,与别的方法对照结果吻合。     

金属铀中铜的极谱测定

本工作用磷酸三丁酯-二甲苯在6N硝酸介质中预先萃取分离铀,应用1.0M水杨酸钠-0.5M氢氧化钠作支持电解质,用极谱法测定了金属铀中的微量铜。测定范围为3.0×10~(-2)—3.0×10~(-4)%,精密度小于±10%,一人完成五个试样分析需8小时。     

IDR生产线氢氟酸中铀浓度分析

建立了一种用于测定干法生产线副产品氢氟酸中铀含量的方法。利用硝酸与氢氟酸在沸点上的显著差异,使样品在浓硝酸作用下加热至近干以去除其中的氢氟酸,然后用硝酸溶液提取残渣中的铀,形成硝酸铀酰清溶液。硝酸铀酰在铀荧光增强剂的作用下能够产生单一的、具有很高荧光效率的络合物。此络合物能在MUA微量铀分析仪发出的紫外光照射下产生荧光,其荧光强度与样品溶液中的铀浓度成正比,采用标准加入法直接用微量铀分析仪测定待测样品溶液中的铀浓度,从而计算出氢氟酸中铀含量。本方法检出下限为0.05×10-3μg/mL;线性范围0.15×10-3~4.0μg/mL;回收率在92%~105%之间;相对标准偏差优于6.0%。该方法用于IDR副产品氢氟酸中铀含量分析,取得了满意的结果。     

TOPO萃取色层分离-ICP-MS法测定土壤中痕量铀的同位素丰度比

为了测定土壤中痕量铀的同位素丰度比,对TOPO萃取色层分离环境样品中U的方法进行了探讨。通过对色层柱体积、吸附酸度、洗涤酸度,以及不同洗脱剂的条件实验,确定了分离流程。获得U的全程回收率为(98.1±1 5)%,对土壤样品中基体元素的去污因子为1 4×103～1 8×105。通过对不同丰度铀同位素标样的测量,确定了ICP MS测量铀同位素的质量偏倚系数。采用了扫描和跳峰两种数据采集方式,获得235U/238U的相对标准偏差优于1%,234U/235U,236U/235U,234U/238U和236U/238U的相对标准偏差优于5%。两种方式测量实际样品的结果吻合。     

土壤中^90Sr的分析测定

对离子交换技术应用于土壤中~(90)Sr的测定进行了条件试验和验证,提出了适用于土壤和海底沉积物样品中~(90)分析的程序。此法在分析50g的海底沉积物和100g的土壤样品时Sr的化学回收率分别为(70.4±10)％和(78.1±11.5)％;Y的化学回收率分别为(83.6±4.0)％和(83.6±5.1)％样品中存在10g Ca和140mg Ba时,不影响Sr的分离和测定。本程序对~(226)Ra的去污因子为1.4×10~3,对混合裂变产物的去污因子大于6.7×10~3。用国产FJ2603 αβ弱放射性测量仪对~(90)Sr的子体~(90)Y进行200min β计数,本法的最低检测限为0.086Bq/kg。     

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.