色层分离—原子吸收／火焰光度法测定UO2中痕量碱金属元素

色层分离-原子吸收/火焰光度法是为分析测定动力堆元件、UO_2粉末和芯块中痕量Li、Na、K和Cs而研究建立的标准分析方法。样品用HNO_3溶解后调成5.5 mol·l~(-1)HNO_3介质,通过TBP色层柱,将待测元素与U分离。分别用FAAS和TAES法测定淋洗液中的Li、Na、K和Cs。取样量为0.5g时,4个元素测定下限均为2×10~(-6)。K和Na含量为10×10~(-6)、Li和Cs为5×10~(-6)时,加入回收率为96%-106%。相对标准偏差在7%以内。     

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%。     

阳离子交换分离ICP-AES法测定高放废液中微量钌、铑、钯

用盐酸及氯化钠处理后的高放废液试样,通过强酸型阳离子交换树脂柱,杂质元素被吸附在树脂上,Ru、Rh和Pd以氯络阴离子形式存在,流入淋洗液中。分离纯化后的试液用ICP-AES法测定其中Ru、Rh和Pd的含量。Ru含量在(35—230)×10~(-6)范围内,重加回收率为90%,相对标准偏差(RSD)为6%;Rh含量在(2—20)×10~(-6)时,重加回收为106%,RSD为10%;Pd含量小于2×10~(-6)时重加回收为72%。     

ICP—AES法测定陶瓷UO_2芯块粉末标准物质中Al、Ba、Co、Ta、Ti和V

本法采用237—季铵萃取树脂,利用萃取色谱分离技术,将陶瓷UO_2芯块粉末中铀与待测杂质元素在6.5mol/L HNO_3介质中定量分离后,用975型ICP直读光谱仪同时测定流出液中Al、Ba、Co、Ta、Ti和V,取样300mg时,测定下限为0.016×10~(-6)-0.25×10~(-6),RSD<7.5％。分析结果均落在标准值的置信区间内。     

连四硫酸根离子-聚氯乙烯膜选择电极的研制及在铀水冶工艺中的应用

叙述了连四硫酸根离子选择电极的研究工作。该电极采用含季铵盐的PVC膜。电极膜的最佳组分为2%的三庚基十二烷基铵(THDDA)、68%的邻苯二甲酸二(2-乙基己)酯(DEHP)和30%的聚氯乙烯(w/w)。在1×10~(-1)～1×10~(-5)mol/L S_4O_6时,S_4O_6~(2-)选择电极具有线性响应并且其斜率符合能斯特方程的理论值,电极的检测限为1×10~(-6)mpl/L。在pH值为4.5到10时,膜电位不变化。测定了各种阴离子的选择系数,S_2O_6~(2-)为4.4×10~(-3);S_3O_6~(2-)为1.4×10~(-1);SO_4~(2-)、S_2O_3~(2-)和SO_3~2为10~(-5)。铀矿碱浸液中连四硫酸盐的浓度可以直接用S_4O_6~(2-)PVC离子选择电极进行测定,测定下限为10mg S_4O_6~(2-)/L,相对标准偏差为±10%。     

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。     

二氧化铀中希土元素的活化分析

在照射前先用TBP萃取-阴离子交换法从大量铀中分出极微量的希土,并制成活化分析的样品,利用反应堆的中子流进行照射(活化)。照射过的样品经过溶解,氟化物、氢氧化物沉淀(或再进行草酸盐沉淀)纯化。最后用阳离子交换法分离各个希土,测量其放射性,从而分别定量测定其含量(在一定条件下可不用阳离子交换法分离,而直接分解衰变曲线)。本法应用于二氧化铀中希士元素的分析,得到满意的结果。其精密度为30%左右。各元素的分析灵敏度(每克样品中能检出的该元素含量):Dy5×10~(-10)克、Gd5×10~(-9)克、Eu5×10~(10)克和Sm1×10~(-9)克。本法可作为希土元素分析(如光谱分析)的对照分析方法。     

高灵敏高效液相色谱法测定地质样品中的U和Th

本文开发了一种新的高效液相色谱(HPLC)法,并应用于地质材料中U和Th含量的测定。首先用HF-HClO_4和HCl浸提液在螺旋盖Savillex烧杯中酸消解岩石样品,然后Th和U用定量的两步离子交换法从地质基体中分离出来,最后采用HPLC进行元素测定。Th和U在反相交换柱上用梯度淋洗,10min即互相分离,而且剩余基体元素以α-羟基异丁酸(HIBA)络合物形式与Th和U分离。在与偶氮胂Ⅲ在线后置柱反应之后,Th和U的测定是用可见分光光度测定法完成的。Th和U的检测限分别约为30×10~(-12)和100x10~(12)(或约0.75×10~(-9)和约2.5×10~(-9),用100mg岩石样品)。 HPLC技术已应用于评价分析特性的9种国际参考样品和3种性能良好的管理样品分析。分析样品中Th和U的浓度范围为<10×10~(-9)～>10×10~(-6),HPLC数据与火花源质谱、电感耦合等离子体(ICP)和同位素稀释热电离质谱分折的数值完全吻合。对Th和U含量分别高于50×10~(-9)和5×10~(-9)的测量,方法精密度在1σ置信水平时分别好于±2％和±5％。     

阳离子交换分离、感耦等离子-原子发射光谱测定REE、Y、Sc和Hf

应用微量修正建立离子交换程序,随后以感耦等离子-原子发射光谱法(ICP-AES)完成地质样品中低含量REE、Y、Sc和Hf测定。偏硼酸锂熔融随后溶解在稀盐酸中,以确保全部样品溶解。样品溶液装入含有AG50W-X8阳离子交换树脂的柱内,使用1.75mol/LHCI再加上1.75mol/LHNO_3淋洗分离不需要的元素。使用这一过程可分离除去几乎所有可能存在的干扰元素(Ba和Zr仍保留),残留的干扰元素的干扰效应很容易校正。样品里存在的Hf、REE、Y和Sc一起用含少量草酸的6mol/LHNO_3洗提下来。通过ICP-AES方法分析获得的分析数据,经鉴定它们对大多数地球化学的应用,其准确度和精密度(±5％)较理想。Y、Sc和Hf检测限分别为0.2×10~(-6)、0.1×10~(-6)和0.2×10~(-6)。     

石墨中微量氯的分光光度测定

本文提出了石墨中微量氯的分光光度测定法,即将石墨样品在氧气流量为400—450毫升/分,温度已为830—880℃的条件下燃烧,氯化物经高温水解后被10%H_2O_2吸收,然后于H_2O_2吸收液中加入NaOH,蒸发除去H_2O_2之后,以Hg(SCN)_2和Fe(NO_3)_3比色测定氯。本法简便,不需分离,影响因素少。对于1克试作,方法的测定下限为1×10~(-4)%。含量为1.9×10~(-4)%时,6次测定结果的相对标准偏差为±14%。加入试验的回收率在85%以上。     

Identification of radiation treatment of wheat （Triticum aestivum. L）and rice （Oryza sativa. L） samples using thermoluminescence of contaminating minerals

Food irradiation is gaining popularity worldwide and this technology is important to improve quality and reduce the post harvest losses of food. Because of the rapid commercialization of irradiated foods throughout the world, compliance of different regulations relating to use of technology in different countries and demand of consumers for clear labelling of irradiated foods, there is need for the development of analytical methods to detect radiation treatment of food. Among several methods studied so far, thermoluminescence （TL） is an important method that can be used to find out the irradiation history of food that contain even a very minute amount of dust particles. In this study, the irradiated and unirradiated wheat and rice samples were analyzed using the TL method. The samples were purchased from the local market of Peshawar and irradiated to radiation doses of 0.5 and 1.0 kGy using Co-60 gamma irradiator at the Nuclear Institute for Food and Agriculture （NIFA）, Peshawar. The mineral contaminants were isolated by jet water, ultrasonic treatment, and density gradient. TL glow curves of the isolated minerals from irradiated and unirradiated samples were recorded between the temperature ranges of 50-500℃ using a TL reader. Generally, the glow curves for irradiated samples showed much higher TL intensities （TL1） than the unirradiated samples. The results were normalized by rerradiation of mineral samples to gamma-ray dose of 1.0 kGy followed by determination of the second glow curves （TL2）. The ratio of the area of first glow curve to that of second glow curve （TL1/TL2） was calculated for selected temperature intervals and compared with the recommended values for unirradiated and irradiated samples. Finally, the shapes of the glow curves for irradiated and unirradiated samples were also analyzed. On the basis of these results （comparison of TL-intensities, TL1/TL2 ratios and shapes of the glow curves）, all the irradiated and unirradiated samples of wheat and rice were unequivocally identified.     

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。     

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.     

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.     

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.     

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.     

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.