首页> 外文会议>International Conference on Environmental Remediation and Radioactive Waste Management >MODELLING ~(226)RA, ~(222)RN, AND ~(210)PB MIGRATION IN A PROPOSED SURFACE REPOSITORY OF VERY LOW-LEVEL LONG-LIVED RADIOACTIVE WASTE
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MODELLING ~(226)RA, ~(222)RN, AND ~(210)PB MIGRATION IN A PROPOSED SURFACE REPOSITORY OF VERY LOW-LEVEL LONG-LIVED RADIOACTIVE WASTE

机译:建模〜(226)Ra,〜(222)rn,〜(210)Pb迁移在一个非常低水平的长寿的放射性废物的拟议表面储存中

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A generic concept for disposal of very low-level long-lived radioactive waste is currently being evaluated for radium bearing wastes that originated from a historical radium extraction plant at Olen, Belgium. A total volume of approximately 217 000 m~3 of waste with an average radium content of 7 Bq/g has to be disposed of. Upon request by the Belgian National Agency for Management of Radioactive Waste and Nuclear Fuels, NIRAS/ONDRAF, a generic disposal concept was evaluated for the purpose of identifying the minimum disposal concept which guarantees long term safety. Such an analysis would provide useful input to the final design of the disposal concept, as the contribution of the different engineered barriers to the overall safety will have been assessed. The analysis focussed on the migration of ~(226)Ra, ~(222)Rn, and ~(210)Pb to groundwater owing to infiltration of rainwater and the diffusive radon transport via the gas phase to the atmosphere. The generic design considered a waste dump with the contaminated material completely enclosed by a clay barrier. To protect the low-permeability clay from degradation by water and wind erosion, frost and desiccation, burrowing animals, and plant roots, among others, a multi-layer cap was designed to meet these requirements. In the performance assessment calculations, various cases were considered in which one component of the disposal concept was changed at the time. Cases considered included absence of clay layers, effects of hot spots, lower adsorption capacity of various materials, and the effect of separating the radium contaminated material from nearly uncontaminated material. Unsaturated flow calculations were done first to estimate the steady-state water content profile. Knowledge on the degree of water saturation is of paramount importance for radon transport through the gas phase. Based on the steady-state water content profile, advective dispersive transport calculations were done considering the decay chain reaction of ~(226)Ra. In addition to the radon gas flux to the atmosphere, fluxes of ~(226)Ra, ~(222)Rn, and ~(210)Pb to groundwater were also produced. Groundwater flow and transport calculations yielded radionuclide concentrations in a hypothetical well nearby the planned disposal site, whereas biosphere modelling provided the annual doses to the public considering the groundwater pathway and direct inhalation of radon in case of the atmospheric pathway. On the basis of the calculated radionuclide fluxes and doses the importance of the various model parameters and concept components will be evaluated and discussed.
机译:目前正在评估处理非常低级别的长寿放射性废物的通用概念,用于源于比利时Olen的历史镭提取厂。必须处理大约217000m〜3的废物,其平均镭含量为7bq / g。根据Belgian国家的放射性废物和核燃料管理机构要求,为识别最低处置概念的目的,评估了一般处置概念的Niras / Ondraf,为担保了长期安全的最低处置概念。这种分析将为处置概念的最终设计提供有用的输入,因为不同工程障碍对整体安全的贡献将得到评估。由于雨水渗透和通过气相渗透到大气中,分析侧重于〜(226)Ra,〜(222)rn和〜(210)Pb至地下水的迁移。通用设计被认为是用粘土屏障完全包围的受污染材料的废物蒸馏。为了保护低渗透性粘土,通过水和风腐蚀,霜冻和干燥,挖洞,穴居动物和植物根部,其中多层帽设计以满足这些要求。在性能评估计算中,考虑了各种案件,其中在该案件的某个组成部分当时改变。所考虑的病例包括粘土层,热点的影响,各种材料的吸附容量较低,以及将镭污染材料与几乎无污染的材料分离的效果。首先进行不饱和流量计算以估计稳态水含量曲线。关于水饱和度的知识对于通过气相阶段对氡传输至关重要。基于稳态水含量概况,考虑到〜(226)Ra的衰减链反应进行平均分散运输计算。除了向大气中的氡气通量之外,还生产〜(226)Ra,〜(222)rn和〜(210)Pb的助熔剂。地下水流动和运输计算会产生放射性核素浓度在预设的井附近,而在计划的处理现场,而生物圈建模在考虑到地下水途径和直接吸入氡的情况下为公众提供了每年剂量。基于计算的放射性核素通量和剂量,将评估和讨论各种模型参数和概念组件的重要性。

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