铀微粒定位及转移技术的研究

在裂变径迹法筛选铀微粒的技术中,热中子辐照后如何实现微粒与径迹的对应以及微粒的转移是非常关键的步骤。采用激光烧蚀仪在介质膜与裂变径迹基片分离前刻蚀出标记,根据标记形状及微粒间的相对位置可实现微粒与径迹的对应关系,不需要介质膜与径迹片复位。采用微区溶解的方法,显微镜下手工挑出微粒并用热表面电离质谱仪对其同位素比值进行了分析。     

4 一体化总中子探测仪的研制

裂变径迹-显微操作技术是定位、转移擦拭样品中含铀微粒的有效技术手段，对于含铀微粒稀少的样品更具优势。本工作研究并建立了利用裂变径迹来寻找含铀微粒、用微操作器对含铀微粒进行转移的方法。     

α径迹法用于分辨高浓铀和Pu微粒的方法研究

擦拭样品微粒分析技术是核保障环境样品分析的一种主要手段，从大量灰尘颗粒中识别并定位含高浓铀（HEU）或含Pu微粒是微粒分析首先需要解决的问题。本文以HEU和Pu微粒为研究对象，建立了用于微粒α径迹测量的样品制备方法，采用CR-39固体径迹探测器为α径迹探测器，测量了不同蚀刻时间2种微粒产生的α径迹星的径迹参数。结果表明：可通过测量径迹短轴与曲率直径并作图来分辨HEU和Pu微粒，该方法对于蚀刻时间大于10 h的微粒径迹星，均能明显分辨，对于径迹非常密集的径迹星，也能准确分辨。     

用裂变径迹法进行铀矿普查

用裂变径迹法测定了铀矿普查现场水样的铀含量,在10~(-4)-10~(-8)g/1范围内,所得结果与荧光比色法和激光荧光法基本符合;对低钠含量样品(≤10~(-8)g/1),用其他方法不能给出确切数据,用裂变径迹法也能给出可供参考的铀含量数值。利用实测样品,对裂变径迹法的重复性进行了研究。最后,对水中杂质含量对测量结果的影响进行了分析和讨论。     

CRM铀微粒的FT-TIMS分析方法研究

在核保障环境取样分析中,对含铀单微粒进行元素和同位素分析是十分重要的。裂变径迹(FT)与热表面电离质谱(TIMS)联用是一种公认的微粒同位素分析技术路线。本文报道了一种改进的FT-TIMS分析方法,方法分为3步：将微粒分散到火棉胶、乙酸异戊酯混合溶液中,然后将溶液平铺在光滑、洁净的玻璃表面上,干燥后形成具有一定厚度的薄膜;将薄膜放入反应堆进行辐照,取出薄膜后将其蚀刻,通过显微镜寻找以及定位铀微粒并将含有铀微粒的部分薄膜分割出来;将分割出来的含有铀微粒的薄膜制样后,用TIMS进行同位素分析。结果表明,这种方法可实现铀微粒的准确定位,有效地解决了铀微粒定位误差问题;同时避免了在微粒转移过程中可能发生的微粒丢失情况;对于CRMU200微粒,²³⁵U/²³⁸U测量值与参考值偏差在2%以内。     

北京市自来水中痕量铀的测定

水中痕量铀的测定,长时间来使用的方法有分光光度法、质谱法、荧光法、活化分析法、极谱法及水化学法等。近年来发展了一种新的痕量铀测定方法——裂变径迹分析法。 裂变径迹分析法是应用热中子诱发样品中~(235)U核发生裂变。裂变碎片在绝缘材料(如云母、玻璃和塑料等)中能造成辐射损伤。这些损伤痕迹经化学蚀刻便成为在光学显微镜下可     

裂变径迹法测铀在铀矿勘探中的应用

裂变径迹法测铀,具有灵敏度高、铀含量与径迹数线性关系好以及不受其它放射性元素干扰等优点。我们用这种方法分析了华南地区3701矿床ZK1005号钻孔的岩心样品,研究了裂变径迹法测铀在铀矿勘探中的应用效果。 1.分析方法 先将样品粉碎,过筛(<160目)、称量,再用盐酸和过氧化氢溶液溶矿。具体方法如下:取0.5克矿粉放在100毫升烧杯中,稍用水浸湿,再加入10毫升盐酸和2毫升过     

裂变径迹法分析水、血液和牙膏样品中的铀含量

本文介绍用裂变径迹法分析各种水样、血样、尿样及几种牙膏样中铀含量。讨论了样品径迹的稳定性和可信件。该方法分析铀灵敏度高、样品用量少、操作简便、结果稳定、耗费低廉,对批量样品分析尤其方便,有广泛的发展前途。     

SIMS微粒分析制样装置研制

二次离子质谱(SIMS)微粒分析的目的是通过分析擦拭样品中的单个感兴趣微粒的同位素比来探知未申报核活动,将擦拭样品上的微粒回收到样品垫上是整个分析流程的第一步,微粒回收率直接影响其对未申报核活动的探知能力。本工作以空气动力学理论计算为基础,采用空气动力学模拟软件对微粒在回收装置内的运动状况进行了模拟,以此设计优化了回收装置结构,研究了在样品垫上附加捕集材料以提高回收率的方法。结果表明：新型擦拭样品回收装置回收率稳定、回收区域集中、微粒分散性较好。对于1 μm的含铀微粒,在不考虑棉布残余含铀微粒的情况下,微粒回收率约为70%,与软件模拟结果一致,在考虑棉布上残余含铀微粒的情况下,微粒回收率约为45%;采用阿皮松作为捕集材料能有效提高微粒回收率,而较长的烘烤时间、较高的烘烤温度能有效降低多原子离子带来的本底干扰,此时其对微粒主同位素分析的影响可忽略。     

裂变径迹法在花岗岩铀配分及蚀变过程中铀的再分配研究中的应用

花岗岩中铀的配分以及蚀变过程中铀的再分配研究,对探讨铀的来源及铀矿成因占有重要位置。本工作采用诱发裂变径迹相对比较法测定岩石和矿物中铀含量和空间分布,进而进行铀配分的研究。 1.实验 相对比较法是将铀标准片(已知铀含量的玻璃)与样品在相同条件下进行照射、蚀刻,从待测样品的径迹密度与标准片的径迹密度之比,求出待测样品的铀含量。     

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.