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首页> 外文期刊>Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine >Monte Carlo simulation and radiometric characterization of proton irradiated (18O)HO for the treatment of the waste streams originated from (18F)FDG synthesis process.
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Monte Carlo simulation and radiometric characterization of proton irradiated (18O)HO for the treatment of the waste streams originated from (18F)FDG synthesis process.

机译:质子辐照的(18O)HO的Monte Carlo模拟和放射学表征,用于处理源自(18F)FDG合成过程的废物流。

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The aim of this work is quantifying the radionuclidic impurities of the irradiated [(18)O]water originated by the [(18)F]FDG synthesis process, and characterizing, from a radioprotection point of view, the waste streams produced. Two samples of 2.4ml [(18)O]H(2)O, contained in two different target cells, have been irradiated with a proton current of 37muA in a PETtrace cyclotron for about one hour each; after irradiation, without performing any chemical purification process but waiting only for the (18)F decay, they have been transferred in two vials and measured by HPGe gamma spectrometry and, subsequently, by Liquid Scintillation Counting. Previously, Monte Carlo calculations had been carried out in order to estimate the radionuclides generated within the target components ([(18)O]H(2)O, silver body and Havar(R) foil), with the aim to identify the nuclides expected to be found in the irradiated water. Experimental results for the two samples, normalized to the same irradiation time, show practically the same value of tritium concentration (about 36kBq/ml) while gamma emitters activity concentrations exhibit a greater spread. Considering that tritium derives from water activation while other pollutants are caused by activated cell materials released into water through erosion/corrosion mechanisms, such a spread is likely to be attributable to differences in the proton beam shape and position (production of different natural circulation patterns inside the target and different erosion mechanisms of the target cell walls). Both tritium and the other radioactive pollutants exhibit absolute values of activity and activity concentrations below the exemption limits set down in EURATOM Council Directive 96/29.
机译:这项工作的目的是量化由[(18)F] FDG合成过程产生的[[18] O]辐射水的放射性核素杂质,并从辐射防护的角度对产生的废物流进行表征。包含在两个不同靶细胞中的两个2​​.4ml [(18)O] H(2)O样品已在PETtrace回旋加速器中用37μA的质子电流辐照了大约1个小时;辐照后,不执行任何化学纯化过程,仅等待(18)F衰减,将它们转移到两个小瓶中,并通过HPGeγ光谱仪进行测量,然后通过液体闪烁计数进行测量。以前,为了估计目标组分([(18)O] H(2)O,银体和Havar(R)箔)中产生的放射性核素,已经进行了蒙特卡洛计算,目的是识别核素。预期在辐射水中被发现。将两个样品的实验结果归一化为相同的辐照时间,结果表明practical浓度值几乎相同(约36kBq / ml),而γ发射体的活性浓度分布更大。考虑到tri来自水活化,而其他污染物是由通过腐蚀/腐蚀机制释放到水中的活化细胞材料引起的,这种扩散很可能归因于质子束形状和位置的不同(内部产生不同的自然循环模式)靶细胞和靶细胞壁的不同腐蚀机制)。 ium和其他放射性污染物均显示出绝对活度值和活度浓度,其值低于EURATOM理事会第96/29号指令规定的豁免限值。

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