~(117)Sn~m标记HEDTMP的研究

合成了亲骨性的氨基膦类化合物HEDTMP（羟乙基乙二胺三甲撑膦酸），研究了^117Sn^m(Ⅳ）标记HEDTMP的条件、标记物的稳定性、亲脂性及在小鼠体内的分布。结果表明，^117Sn^m(Ⅳ）与HEDTMP在常温下反应5min即可形成标记率大于95％的配合物；酸度和配体量对溶液外观有较大的影响，但不影响标记率；^117Sn^m(Ⅳ）－HEDTMP的稳定性较好，属亲水性配合物。上鼠体内分布实验表明，配合物主要为骨骼提取，其它组织的摄取趋于本底。     

188Re间接标记单克隆抗体的研究

采用先标记后偶联的方法,以NHS－MAG3为双功能连接剂,研究了用^188Re标记单克隆抗体的各种实验条件,得到了最佳标记方法和偶联方法。标记抗体^188Re-NHS-MAG3-IgG体外稳定性良好。完成了^188Re-NHS-MAG3-GL3在小鼠体内的生物分布实验,结果表明该配合物在体内稳定性良好。     

~(188)Re-DTPA的制备及生物分布研究

以SnCl2·2H2O为还原剂,还原188ReO-4并与DTPA直接配合获得188Re DTPA,优化了标记反应条件;对188Re DTPA和Na188ReO4在正常小鼠体内分布进行了比较。实验结果表明,在最佳标记条件下,188Re DT PA的标记率大于95%;标记物体外稳定,经生理盐水稀释后,其稳定性下降。188Re DTPA在小鼠体内血液清除快,在甲状腺、胃及其它组织中的摄取率明显低于Na188ReO4,主要经肾脏通过尿液排出体外。     

153Sm配合物与牛血清白蛋白结合对骨摄取的影响

研究了NTMP（次氮三亚甲基膦酸），HEDTMP（N－（羟乙基）乙二胺基三亚甲基膦酸），DCTMP（1，2－环己二胺四亚甲基膦酸），EDTMP（乙基二胺基四亚甲基膦酸），DTPMP（二乙基三胺基五亚甲膦酸），DTPA（二乙基三胺基五醋酸）的^153Sm配合物在羟基磷灰石（HA）和I型骨胶原上的吸附及其在小鼠体内的骨摄取，观察到体内骨摄取与体外骨模型吸附性能的差别。在对上述6个^153Sm配合物与牛血清白蛋白（BSA）的结合性质研究中观察到，^153Sm配合物与BSA的结合性对其骨摄取过程有重要影响，并解释了^153Sm配合物体内骨摄取与体外骨模型吸附不一致的原因。     

~(153)Sm-TTHMP的合成及在小鼠体内的分布

制备了三乙烯四胺六甲撑膦酸（TTHMP）的^153Sm标记物，研究了其标记条件、体外稳定性、化学计量组成、兔SPECT骨扫描及在小鼠体内分布。结果表明，在pH＝7．0－8．5时，高配体时有助于标记物的形成；标记物稳定性高，7d内放化纯度基本保持不变；本实验条件下制备的标记物的化学计量组成为n（^153Sm）：n（TTHMP）＝1：1，兔骨骼显像和小鼠体内分布表明，标记物主要为骨骼系统摄取。     

153Sm-HEDTMP的标记及小鼠体内分布研究

制备了经乙基乙二胺三甲撑膦酸(HEDTMP)的^153Sm标记物，研究了标记物的标记条件、体外稳定性、化学计量组成、免SPECT骨扫描及小鼠体内分布。结果表明，弱碱性介质、高配体量有助于标记物的形成，中性、弱碱性介质和高配体量有利于标记物的稳定，实验条件制备的标记物的化学计量组成为^153Sm：HEDTMP=1：1，免骨显像和小鼠体内分布表明标记物主要由动物骨铭系统摄取，是非常有希望的骨肿瘤缓解治疗剂。     

~(117)Sn~m(~(188)Re、~(153)Sm)-EDTMP的制备及在小鼠体内的生物分布比较

本工作通过合成得到配体EDTMP,制备出标记率较高的117Snm(188Re、153Sm)配合物。对3种配合物的体外稳定性、亲脂性进行了考察;对其生物分布作了初步探索,评价了188Re-EDTMP、117Snm-EDTMP作为骨肿瘤治疗药物的可能性。结果表明,3种配合物都易于被骨摄取,但188Re-EDTMP的体内稳定性较差,容易被洗脱,需要进一步改善;与已用于临床应用的153Sm-EDTMP相比,117Snm-EDTMP的小鼠体内分布与其趋势比较一致,在靶组织(脑骨和四肢骨)上的浓集率较高,显示出可用于骨系统疾病治疗的可能性,有进一步研究的价值。     

~(99)Tc~m-膦混配配合物的制备和生物分布

合成了一个N3S配体（MVNM）和4个膦配体，并以配体交换法在室温下制备了^99Tc^m－MVNM，然后分别与4个膦配体发生混配反应，得到放化纯大于90％的^99Tc^m－MVNM－膦混配配合物。小鼠体内的生物分布实验表明，该类混配配合物有一定的心肌摄取。     

188Re-NEPTDD的制备及生物分布研究

在首次合成NEPTDD(2,2,9,9-四甲基-4,7-二氮-4-乙撑哌啶-1,10-二硫癸烷)的基础上,采用SnCl2作还原剂制备了^188Re-NEPTDD。研究了^188Re-NEPTDD的生理盐水溶液通过尾静脉注射后在小鼠体内的生物分布及该配合物的碘化油溶液通过肝动脉灌注后在大白兔体内的生物分布;用SPECT扫描得出配合物的碘化油溶液通过肝动脉灌注后的大白兔全身显像。实验结果表明,^188Re-NEPTDD具有理想的肝摄取,肝部的摄取和滞留较为主要。肝部显像清晰。非靶组织(特别是肺)的摄取和滞留低。     

^188Re—AEDP的标记条件研究

用^188W/^188Re发生器淋洗得到的^188Re研制具有潜在临床应用价值的骨疼痛治疗剂^188Re-AEDP。研究了在不同配体用量、亚锡含量和pH条件下,载体用量对标记率和稳定性的影响。实验结果表明：在最佳条件（pH1.10,AEDP20mg/mL,氯化亚锡2mg/mL,抗坏血酸3mg/mL)下,用无载体^188Re标记的^188Re-AEDP的标记率为９０％－９３％;标记后调pH为6,24h后放化纯度为70％;而用含一定量载体的^188Re标记的标记率为95％－98％,标记24h后放化纯度为93％。     

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.