~(99)Tc~m-MPAQ的合成及其生物分布

为寻找新的^99Tc^m脑灌注显像剂，对^99Tc^m-MPBDA进行了结构修饰。在制备N-(2-巯基丙基)-1，2-苯二胺(MPBDA)基础上合成了三齿配体8-[N-(2-巯基丙基)]-氨基喹啉(MPAQ)，产物经IR，^1H NMR，MS及元素分析等表征确认。以氯离子为单齿配体，用直接标记法制备了^99Tc^m—MPAQ，确定了最佳标记条件，测定了标记物的稳定性和脂溶性。实验结果表明，^99Tc^m-MPAQ放化纯在96％以上，室温下在水溶液中稳定6h以上，脂溶性比^99Tc^m-MPBDA的大。生物分布试验结果表明，^99Tc—MPAQ生物性质没有^99Tc^m-MPBDA的好，但它可以穿过正常的血脑屏障，有-定的脑摄取(1．55％／g)和脑滞留(注射后30min仍有初始摄入量的62%).     

99Tcm标记趋化肽类似物的制备

利用固相法合成趋化肽类似物fMLFK,并采用双功能螯合剂(HYNIC)技术合成了^99Tc^m标记的趋化肽类似物^99Tc^m-HYNIC-fMLFK,测定了标记物的标记率和放化纯度,考察了配合物的稳定性。结果表明,合成fMLFK的产率大于80％,纯度大于97％;质谱法测得的相对分子质量与理论值相符;^99Tc^m标记后,配合物的放化纯度大于95％,在24h内放化纯度无明显降低。     

99Tcm-MAG3-Lys-mPEG的制备及其在小鼠体内的分布

以mPEG-5000、Fmoe-Lysine和MAG3为原料，经过五步反应合成了载体MAG3-Lys-mPEG；对其进行^99Tc^m标记后，进一步研究了标记物的体外稳定性及其在小鼠体内的生物分布。结果表明，^99Tc^m-MAG3-Lys-mPEG的标记率〉98％；标记物在体外有很好的稳定性，在生理盐水中放置24h时，放化纯度〉91％；在血清中温浴16．5h时放化纯度仍〉92％；标记物在小鼠体内的血液清除较快，在肾脏中的摄取最高，标记物主要经肾脏通过尿液排出体外。mPEG有可能用作反义核酸的有效载体。     

5 ^99Tc^m（CO）3-IDA-FAC11的制备及生物分布

放射性核素标记脂肪酸作为心肌代谢显像剂可进行局部缺血定位及评价梗塞区心肌的活力。在SPECT显像药物中，锝[^99Tc^m]药物占有主导地位，因此，^99Tc^m标记的心肌脂肪酸代谢显像剂将有非常好的应用前景。本实验对象为二（N-乙酸）-十一烷酸（HOOC（CH2）10N（CH2COOH）2，IDA—FAC11），以[^99Tc^m（CO）3（H2O）3]^＋为中间体，合成了^99Tc^m（CO）3-IDA—FAC11，建立了^99Tc^m（CO）3-IDA—FAC1l放化纯的高效液相色谱法（HPLC）分析方法。研究了反应时间、温度、pH值和配体用量等对标记物产率的影响。     

Gd—DTPA—Dimeglumine的^99Tc^m标记及其生物学特性

以氯化亚锡为还原剂,^99Tc^m一步法标记了顺磁对比剂Gd—DTPA-Dimeglumine（钆喷酸二甲葡胺）,得到^99Tc^mGd-DTPA-Dimeglumine。薄层色谱法（TLC）分析标记物的标记率〉95％,可在室温稳定存放6h,放化纯度〉90％;三氯乙酸沉淀法测定^99Tc^m-Gd—DTPA-Dimeglumine的体外血浆蛋白结合率为2．25％±0．21％。小鼠体内生物分布结果显示,^99Tc^m-G＆DTPA—Dimeglumine主要经肾脏排泄,脑和肌肉组织摄取最少,所有脏器在注射后1min摄取达高峰,注射后5min滞留率下降大于50％,注射后30～60min标记药物在主要脏器内滞留很少,家兔肾动态显像结果显示,^99Tc^m-Gd—DTPA-Dimeglumine主要经肾脏排泄,达高峰时间约5min 半排时间约7min。^99Tc^m标记Gd-DTPA—Dimeglumine方法简单,标记效率高,Gd-DTPA—Dimeglumine经^99Tc^m怀记后其生物学性质基本未改变。本实验表明可以通过双功能螯合剂DTPA同时链接放射性核素^99Tc^m和顺磁性金属元素Gd,并有望在此基础上合成一种具有较好靶向性又可同时进行核医学SPECT和MRI增强扫描的显像剂。     

肿瘤受体显像剂99Tcm-octreotide的放化纯度分析

采用高压液相色谱分析(HPLC)和双层析结合银染色两种方法，对新型肿瘤受体显像剂^99Tc^m—oc—treotide的放化纯度进行分析。结果表明，双层析法结合银染色可以准确、有效地分离^99Tc^m—octreotide及其它放射性组分，可以较精确地计算出显像剂的放化纯度。为Octreotide及其它多肤类显像剂的放化纯度测定提供了一种简捷、准确的新手段。     

一种99Tcm标记的5-HT1A受体显像剂的合成与标记

合成了一种^99Tc^m标记的5-HT1A受体显像剂。该显像剂先由二硫二氮与6-溴己酰氯结合，再与2-（1-哌嗪）苯甲醚结合，经还原、脱保护反应得到标记前体，再对前体进行^99Tc^m标记。标记率达90％以上，薄层层析测得标记物放化纯度大于95％。     

~(99)Tc~m标记的N-(邻甲硫基苯基)乙二胺和硫醇混配配合物的制备及生物分布

合成了新的三齿配体N-(邻甲硫基苯基)乙二胺(MTPEA)，并经IR、元素分析、MS(FAB^ )表征确认。确定了混配配合物^99Tc^m(L3,L1s)(L3为MTPEA，L1s为乙硫醇)和^99Tc^m(L3，L1b)(L1b为异丙硫醇)的最佳标记条件。标记物在小鼠体内的生物分布结果表明：这两种配合物都可以通过正常的血脑屏障，并在脑中有一定的滞留。在注射后2，30min，^99Tc^m(L3，L1s)的脑摄取值分别为2．09％／g和1．10％／g；^99Tc^m(L3，L1b)的脑摄取值分别为1．76％／g和l.08％／g。     

^99Tc^m标记硫酸软骨素及其在小鼠体内的生物分布

采用亚锡还原法对硫酸软骨素（CS）进行了^99Tc^m标记,优化了标记条件,并观察标记物在小鼠体内的生物分布,为骨关节软骨显像提供依据。采用薄层层析分析标记产物的标记率为81．6％±1．7％;用直径为0．2p．m的无菌滤膜对标记液纯化,纯化后放化纯度为90．1％±1．2％^99Tc^m—CS在小鼠体内的生物分布结果显示,其在血液中清除较快,肾脏是主要排泄器官;有较高的亲软骨组织特性,4h时软骨与血液的放射性摄取比（T／NT）为8．31,软骨与骨的T／NT为2．03。以上结果提示,^99Tc^m-CS的标记方法简便,有一定的亲软骨组织性,有待进一步研究。     

MAG3在放射性金属标记应用中的最新研究进展

综述了利用巯乙酰基三甘氨酸(MAG3)标记的多肽的生物学特性。经MAG3形成的^99Tc^m标记物的标记率和比放射性高,体内稳定性好,与血清蛋白的非特异性结合低;经MAG3形成的^186/188Re标记物也具有良好的体内外稳定性。     

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.