美国Beckman公司和上海原子核所的~3H 和~(14)C液闪猝灭校正系列源的比较和评价

本文比较了上海原子核所和美国 Beckman 公司的~3H 和~(14)C 猝灭校正系列源。对~3H 猝灭系列源,原子核所和 Beckman 自身校正的偏差(给定的活度与校正后活度之差除以给定活度)相近,均值±(单次)标准差分别为-1.26±1.66%和1.08±1.96%(n=10);互校偏差略大,原子核所源校 Beckman 源的偏差均值士标准差为-2.63±1.52%(n=9),反之为2.47±1.67%。对~(14)C猝灭系列源,上述四值分别为-0.13±1.1%和0.077±0.55%及0.25±0.93%和0.30±2.09%(n=10)。两单位的猝灭系列源有较好的一致性,且适于常规的仪器校正之用。     

毫居里级~(60)Co标准源的制备

本文详细介绍一种制备 mCi 级钴标准源的方法。将一根约13mCi 的钴丝分成三段,并用高压电离室精确测定其相对强度;取其放射性最弱的一段为参考样;溶于盐酸,经定量稀释制成~(60)Co参考样溶液,绝对测量参考样溶液的比活度;结合稀释比和相对强度,分别测定参考样和另二段钴丝的绝对活度,得到二个标准钴源的活度为7.747_3±0.055mCi 和3.056_2±0.022mCi(参考日期1983.11.3)。参考样溶液比活度的绝对测量,采用4πβ-γ符合法和液体闪烁法两种方法,两者在0.3%范围内一致。     

^131I放射性活度的相对测量

本文报道选用与样品源相同的核素作标准源,运用稳定性较好的探测仪器,控制样品源与标准源测量时的相同几何条件,进行比对源~(131)I活度的相对测量,~(131)I测量值为672.6±4.7Bqmg~(-1),与4πβ-γ符合活度基准测量值670.8±2.7Bqmg~(-1)和各比对单位上报结果平均活度671.1±1.7Bqmg~(-1)相对误差均低于3‰,比对结果颇为理想,说明相对测量方法乃是目前基层放射性监测单位测量放射性活度行之有效的方法。     

高活度钴-60治疗源的就地倒装

高活度钴-60治疗源装机以后,有时因钴源装配不当,或抽屉移动阻滞而使钴源位置不重复,下能使用。在生产厂与钴源使用单位相隔较远的情况下。解决这类问题,只有就地倒装是最经济、合理的办法。本文以实例介绍了这种倒装的方法和应考虑的主要问题及其结果。     

标准放射性活度测量仪计量特性与控制

文章介绍了该实验室标准医用放射性活度测量装置的计量特性与控制，其各项性能指标均优于国家标准级活度测量仪检定规程所限定的要求。测量总不确定度小于±4％，经检定10种常用核素活度测量总不确定度均在±3．8％以内，57Co、241Am、137Cs、60Co4种核素，参加了全国核素活度计量比对，利用该装置测量提供的数据均在标准均值的±1．0％以内。多年来对装置进行严格地质量控制，连续3年用137Cs监督源监测，并建立了长期稳定性监控图，连续6年稳定性均控制在±0．6％以内；连续近两年对3种核素标准源进行测量准确度监测，其测量准确度的复现性137Cs和60Co小于1.0％，241Am小于1.6％。     

高放废液中^126Sn的放化分析

以甲基异丁基酮(MIBK)萃取为主要步骤,放化分离高放废液中的~(126)Sn。全流程化学回收率约为60%。以SnO_2形式制成测量源,用HPGe γ谱仪测取γ谱图,由~(126)Sn的子体特征γ能峰面积,经化学回收率、探测效率校正后,计算得到高放废液中~(126)Sn的含量为371±29 Bq/ml。~(126)Sn的放射性活度约为高放废液总活度的4×10~(-7)。     

井型4πβ+4πγ活度测量装置

4πβ+4πγ活度测量装置由4π流气式正比计数器、井型NaI(Tl)探测器和HPGe探测器构成。将4π流气式正比计数器放于HPGe探测器上,插入井型NaI(Tl)探测器井中,实现了β射线探测效率、活度和γ分支比的同时测量。测量了60Co、137Cs和166mHo的放射性核素活度,结果分别为:127.64(1±0.34%)、191.68(1±0.27%)和130.17(1±0.21%)Bq/mg,与国内外比对结果符合得很好;同时测量了137Cs和166mHo的主γ射线分支比,与文献值在不确定度范围内一致。     

CN-101 60Co放射源研制

介绍了CN-101型工业辐照用⁶⁰Co密封源的研制过程和产品制备的工艺流程,包括结构设计、原型源试验、钴棒束水下解体、钴棒水下活度测量、钴棒热室切割、封装焊接、泄漏检查、表面污染检查、外形尺寸检查、最终产品活度测量。2011年2月产品通过合格性鉴定,结果表明,产品各项技术指标达到国际先进水平。CN-101密封源的研制成功填补了国内辐照加工业空白,打破了国外产品的垄断,年生产能力达2.035×10¹⁷ Bq。     

一次钴-60污染事件的多机构应急调查测量及其结果分析比较

本文描述了一起涉外钴-60污染不锈钢表带产品部件——表带拆生针剩余坯料的现场取样程序,从已查获的9ks(约32100根)表带拆生针剩余坯料中抽取619根样品,由国内较具权威的三家放射性测量机构对各自样本独立进行测量分析,另一家放射性测量机构参加样品成对测量比对;给出了各放射性测量机构对同一总体中抽取的各自样本的测量分析结果。测量结果表明,所抽取的619根样品中,有141根含放射性钴-60;其钴-60的活度浓度值明显呈两组数据分布。对各机构测量分析的结果,进行了配对t统计检验;结果表明：在95％的显著性水平下,没有理由认为他们测量分析的各自样本中放射性钴-60的活度浓度值不相等。对三家放射性测量机构测量各自样本中样品的放射性钴-60活度浓度值进行合并统计,高值组143个样品,平均值和标准差分别为224．8和11．9Bq／鄯低值组38个样品,平均值和标准差分别为72．4和11．5Bq／g;最大活度浓度值为285．7Bq／g;即使是单根不锈钢表带拆生针坯料样品中的最大活度浓度,也在某国电离辐射防护办公室通报的活度浓度(1000Bq／0．2g)的1／17以下。     

GY-20和GY-40型大容量钴-60运输容器关键技术研究

GY-20和GY-40型大容量钴-60运输容器是为运输工业用钴-60成品源和钴-60棒束而设计的专用设备。由于内容物放射性活度水平高、衰变热大，仅有加拿大、英国、俄罗斯等少数国家具有设计能力。本文综合考虑容器结构、热工、力学、屏蔽等方面的要求，对容器设计和制造过程中的关键技术以及解决方案进行了分析研究。试验验证结果表明，容器的结构设计、包铅边界设计准则的确定和制造过程的质量控制措施合理、有效，能保证容器在各种工况下的屏蔽完整性，容器具有安全运输大容量钴-60源项的能力，其设计满足相关标准和规范要求，可为其他B型货包的设计提供参考。     

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.     

有效探测面积大于1000 cm2的正比计数器测量系统性能测试

为对自制的活性面积高达1 000 cm²的大面积源进行表面发射率定值,同时作为现有2πα、2πβ表面发射率标准装置能力的扩充,研制了一套内置式大面积2π多丝正比计数器测量系统,并利用活性区直径为8 mm的²⁴¹Am点源及活性区面积为10 cm×15 cm的大面积²⁴¹Am和⁹⁰Sr-⁹⁰Y源对其进行计量学性能测试。结果表明：计数器内计数响应均匀性优于±0.4%,有效探测面积达1 400 cm²;所得²⁴¹Am源高压坪曲线的坪长为1 400 V,坪斜为0.27%/100 V,坪区内计数变化为0.87%;⁹⁰Sr-⁹⁰Y源高压坪曲线的坪长为300 V,坪斜为0.75%/100 V,坪区内计数变化为0.80%;10次测量重复性好于0.4%,8 h内短期稳定性好于0.3%,1 a内长期稳定性好于0.8%。     

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.     

Interaction between uranium and humic acid (Ⅰ): Adsorption behaviors of U(Ⅵ) in soil humic acids

The adsorption behaviors of uranium on three soil humic acids (HAs), which were extracted from soils of different depths at the same site, were investigated under various experimental conditions. The adsorption results showed that U(Ⅵ) in solutions can be adsorbed by the three soil HAs, with the order of FHA (HA from 5 m depth of soil) ＞SHA (HA from the surface) ＞THA (HA from 10 m depth of soil) for adsorption efficiency in each desirable condition, and the adsorption reached equilibrium in about 240 min. Although the maximum adsorption efficiency was adsorption could be described with Langmiur isotherm or Freundlich isotherm equation. The L/S (liquid/solid, mL/g)ratio and pH were important factors influencing the adsorption in our adsorption system besides uranium concentration. The adsorption efficiency decreased with the increase of the L/S ratio and pH at the pH range of 2.0-3.0 for SHA and THA or 2.5 - 6.0 for FHA. However, no significant difference in adsorption of U(Ⅵ) was observed at the experimental temperature. All the results implied that humic substances have different characteristics in samples even collected at the same site.     

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。     

The preclinical pharmacological study of dopamine transporter imaging agent 18F-FP-β-CIT

The paper is to study pharmacologic characteristics of 18F-FP-β-CIT (18F-N-(3-fluoropropyl)-2β- carbomethoxy-3β- (4-iodophenyl)nortropane) as an imaging agent for dopamine transporter. The radiochemical purity of 18F-FP-β-CIT in aqueous solution was over 95% after standing at room temperature for 4h. Biodistribution displayed rapid uptake in rat brain (1.375 %ID/organ at 5min and 0.100 %ID/organ at 180 min) and the striatal uptake was 1.444,0.731, 0.397, 0.230 and 0.146 %ID/g at 5, 30, 60, 120 and 180 min, respectively. The values of striatum/cerebellum,striatum/frontal cortex and striatum / hippocampus in rat's brain at 30 min were 3.38, 2.17 and 2.40 respectively. The uptake in striatum can be blocked by β-CFT, suggesting that 18F-FP-β-CIT binds to DAT peculiarly. The compound was rapidly cleared from monkey's blood. The striatal uptake was bilaterally decreased in the left-sided lesioned PD rats, compared with normal control. Brain PET imaging studies in normal monkey showed that 18F-FP-β-CIT was concentrated in striatum. The test of undue toxicity showed that the dose received by mice was 1250 times as by human, which indicates that 18F-FP-β-CIT is very safe. So 18F-FP-β-CIT is a promising PET imaging agent for DAT with safety and validity.     

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.