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An approach for acquiring data for description of diffusion in safety assessment of radioactive waste repositories

机译:在放射性废物处置库安全评估中获取用于描述扩散的数据的方法

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摘要

Repositories for radioactive wastes are sited in the environment with very low permeability. One of the most important processes leading to the release of radionuclides to the environment is therefore diffusion of radionuclides in both natural and engineered barriers. Data for its description are crucial for the results of safety assessment of these repositories. They are obtained usually by comparison of the results of laboratory diffusion experiments with analytical and/or numerical solution of the diffusion equation with specified initial and boundary conditions. Results of the through-diffusion experiments are obviously evaluated by the "time-lag" method that needs for most of sorbing species unfortunately very long time of the experiment duration. In this paper a modified approach is proposed for the evaluation of diffusion data for safety assessment, which decreases the influence of propagation uncertainties using incorrect data and reduces time for acquiring data for safety assessment. This approach consist in the following steps: (i) experimental measurement of material diffusion parameters under various conditions using non-sorbing tritiated water or chlorine for which it is easy to reach conditions under which the "time-lag" method of evaluation of the result of the through-diffusion experiment is applicable-this step provides well established diffusion characteristics of materials for neutral species and anions, then (ii) to evaluate sorption isotherms for sorbing radionuclides from batch experiments under conditions corresponding to composition of material pore water, (iii) to assess the values of effective and apparent diffusion coefficients for sorbing radionuclides from well-defined diffusion coefficients of species in free water and (iv) to verify the obtained results using relatively short-term diffusion experiments with sorbing radionuclides, which will be evaluated using the time dependent decrease of the concentration in the input reservoir of the diffusion cell. A numerical model of the diffusion cell can model the decrease of concentration of species. The code, which we used for this type of evaluation of diffusion experiment, is based on the same approach to modelling that we use for modelling of the diffusion transport in performance assessment studies. The advantage of this approach consists in the compatibility of the approaches used for both evaluation and verification of the laboratory diffusion experiments and performance assessments and in considerable less time needed for experiments.
机译:放射性废物库位于渗透率非常低的环境中。因此,导致放射性核素释放到环境中的最重要过程之一是放射性核素在天然和工程屏障中的扩散。描述数据对于这些存储库的安全评估结果至关重要。通常通过将实验室扩散实验的结果与具有指定初始条件和边界条件的扩散方程的解析和/或数值解进行比较来获得它们。显然,通过“时滞”方法评估了贯穿扩散实验的结果,该方法需要大多数吸附物质,但是实验持续时间很长。在本文中,提出了一种用于评估扩散数据以进行安全评估的改进方法,该方法可减少使用错误数据传播不确定性的影响,并减少获取用于安全评估的数据的时间。该方法包括以下步骤:(i)使用不吸附的using化水或氯气在各种条件下进行材料扩散参数的实验测量,因为这些条件很容易达到“时滞”法评估结果的条件通过扩散实验是可行的-此步骤为中性物质和阴离子提供了公认的材料扩散特性,然后(ii)在与材料孔隙水成分相对应的条件下评估批次实验中吸收放射性核素的吸附等温线,(iii )从游离水中明确定义的物种扩散系数评估吸收放射性核素的有效和表观扩散系数的值,以及(iv)使用相对短期的吸收放射性核素扩散实验来验证所获得的结果,将使用扩散输入池中浓度随时间的降低离子电池。扩散池的数值模型可以模拟物质浓度的降低。我们用于这类扩散实验评估的代码基于与在性能评估研究中用于扩散传输建模的建模方法相同的方法。这种方法的优势在于可兼容用于实验室扩散实验和性能评估的评估和验证,并且实验所需的时间大大减少。

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