18F-FDG制备及应用中的辐射防护评价

采用辐射剂量仪对回旋加速器室、药物合成室、注射室、扫描室的辐射水平进行了监测,为工作人员的辐射防护提供参考.结果表明不同场所γ射线辐射水平变化很大,回旋加速器室、药物合成室的屏蔽结构在γ射线防护方面符合要求;注射室虽放置有防护屏,但照射剂量率仍较高,而且对操作人员的屏蔽防护效果明显低于回旋加速器室和药物合成室;已经注射放射性药物的患者其周围γ辐射水平也较高(3.02±0.62～4.82±0.94 μSv/h).     

1 MeV电子加速器辐射屏蔽防护研究

基于NCRP.51号报告对屏蔽室外关键点的安全性进行理论计算,为湖北科技学院1 Me V高压,50 m A束流强度的电子加速器设计一个屏蔽系统。在电子加速器正常运行情况下,使用辐射防护剂量率仪对屏蔽室周边环境辐射水平进行监测。监测结果满足《γ射线和电子束辐射装置防护检测规范》(GBZ 141—2002)中透射辐射所产生的平均剂量率小于2.5μSv/h,能保证从事辐射加工工作人员及外来人员身体不受辐射损伤,对场地安全性有重要指导意义。     

小型回旋加速器电离辐射自屏蔽装置设计

<正>目前,在用于医用中短寿命同位素生产的回旋加速器中,同位素生产靶系统及加速器本体在运行时会产生中子及γ电离辐射。根据中国现行法规和标准要求需对电离辐射进行防护,并降低到标准要求的剂量率限值,保证放射性工作人员及公众的安全。对于同位素生产用加速器的电离辐射屏蔽通常需较厚的混凝土进行防护,防护手     

γ射线束远距治疗机周围的杂散辐射

在远距治疗用γ射线的防护工作中,为了评价治疗机的防护性能、设计次级防护屏蔽、估算个人剂量、以及采用距离-时间防护技术等等,都需要了解γ射线束远距治疗机周围的杂散辐射水平及其分布特征。斯皮尔施(Spiers)等人曾测量了早期生产的钴-60远距治疗机的杂散辐射水平。随着治疗机设计和工艺方面的改进,其杂散辐射水平与对早期生产的远距治疗机测量的结果相比较,已明显的降低。杂散辐射包括泄漏辐射和散射辐射。前者是指除     

对肿瘤医院放疗科辐射防护水平的评价

本文主要介绍我院放疗科防护设计的原则和计算方法,并对工作场所γ辐射水平实测结果进行了评价。此外还对高能医用加速器16MV X 射线的光中子污染及其防护措施作了初步探讨。     

0.8 MeV单能中子照射洋葱萌发种子后在根尖细胞中诱发微核的相对生物效能

通过由加速器产生的0.8 MeV单能中子和60Coγ射线照射洋葱萌发种子,观察在根尖细胞中微核诱发率,从而更好地了解中子相对生物效能(RBE)。洋葱萌发种子照射单位剂量0.8 MeV单能中子和60Coγ射线后,根尖细胞中的微核诱发率分别为111±6.7(10-2Gy-1)和3.59±0.19(10-2Gy-1)。因此,以60Coγ射线为参考辐射时,0.8 MeV单能中子在洋葱根尖细胞诱发微核的相对生物效能(RBE)值为31.0±2.5。与252Cf裂变中子的RBE比较,0.8 MeV单能中子照射在洋葱根尖细胞中诱发微核的RBE值要高。     

医用直线加速器机房辐射屏蔽分析

为评估机房辐射防护水平,依据机器的运行上限参数,运用相关文献报道的计算方法,对X射线初级和次级屏蔽层以及加速器防护门的屏蔽能力进行估算和分析。结果表明:加速器机房四周墙体(除迷路内墙外)和天棚的设计厚度均大于理论计算厚度,表明机房的相应屏蔽层厚度设计可以满足15 MeV X射线加速器的防护标准及选定的剂量管理目标值;此外,机房防护门需增加8.3 mm铅和6.9 cm含硼聚乙烯才能分别满足对X射线和中子的屏蔽要求。     

基于蒙特卡罗方法的复合材料辐射屏蔽设计北大核心CSCD

在乏燃料后处理厂的工作环境中可能存在着低能中子-γ射线混合辐射,严重威胁工作人员的人身安全。本文针对上述混合辐射环境,利用蒙特卡罗程序Geant4模拟计算了一种钨/硼纤维增强含硼/铋聚合物复合材料中不同材料参数对低能中子和γ射线综合防护效果的影响。结果显示,此种钨/硼纤维复合材料对低能中子和γ射线均具有良好的屏蔽效果。文章证实了纤维垂直排布方式具有比平行排布方式更优的屏蔽效果,且垂直排布方式下透过粒子束的强度分布更加均匀。此外,在聚合物基体中掺杂一定质量分数的硼/铋可以进一步增强复合材料的辐射屏蔽效果。依据这些结果我们认为此种复合材料可以为后处理厂等辐射环境中的防护服及相关防护用具提供参考。     

1.5m 回旋加速器辐射安全评价

本文对1.5m 回旋加速器的屏蔽状况、运行中的辐射安全及其对环境的影响等进行了分析和评价。     

用4道脉冲幅度甄别器[φ4×4英寸 NaI(Tl)为探测器]测量环境天然辐射水平

本文主要介绍以φ4×4英寸 NaI(Tl)为探测器的4道脉冲甄别器,用以测量和区分包括宇宙射线在内的不同成分的环境天然辐射水平的方法。4道:Disr、Ch1、Ch2、Ch3的甄别阈范围设定为使其能记录的γ射线的能量范围(主要包括天然辐射成分)依次约为0.58MeV—∞(~(40)K、铀、钍系核素的γ射线,宇宙射线)、2.0—4.2MeV(铀系~(214)Bi 中能量为2.2MeV 的γ射线,钍系~(208)Tl 中能量为2.61MeV 的γ射线,少量低能宇宙射线)、>4.2 MeV(除少量低能宇宙射线外的全部宇宙射线)、>12.5MeV(能量较高的宇宙射线)。用此方法在中国辐射防护研究院低本底放射性实验室和地下铁室进行了测量,评价了地下铁室的屏蔽效果。文中还给出了在广州—太原和北京—大阪航线的飞机上的测量结果。     

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。     

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.     

PLASMA SCIENCE AND TECHNOLOGY AUTHOR INDEX TO VOLUME 16(2014)

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Radioactivity levels in soil of salt field area,Kelambakkam,Tamilnadu,India

Soil samples in and around salt field area have been analyzed for natural radioactivity concentration using gamma ray spectrometer.The activity concentration for ~(232)Th,~(238)U and ~(40)K are ranged from 27.88 to 45.27 Bq/kg, from BDL to 13.30 Bq/kg,and from 135.54 to 381.28 Bq/kg,respectively.The measured activity concentrations for these radionuclides were compared with world average activity of soil.The average activity concentration of ~(232)Th in the present study is 1.19 times higher than world median value while the activity of ~(238)U and ~(40)K is found to be lower. The absorbed dose rates due to these radionuclides were calculated.The average absorbed gamma dose rate due to the presence of ~(232)Th,~(238)U and ~(40)K in soil samples is 36.99 nGy·h~(-1).These results indicate no radiological anomaly. The data presented in this study will serve as a base line survey for primordial radionuclides concentration in the study area.