首页> 外文会议>International conference on safety of radioactive waste management >MODELLING OF THE MIGRATION OF ~137Cs AND ~60Co RADIONUCLIDES IN THE PRELIMINARY SAFETY ASSESSMENT OF THE NOVI HAN RADIOACTIVE WASTE REPOSITORY. IMPLEMENTATION OF THE EXPERIMENTALLY OBTAINED SORPTION COEFFICIENTS
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MODELLING OF THE MIGRATION OF ~137Cs AND ~60Co RADIONUCLIDES IN THE PRELIMINARY SAFETY ASSESSMENT OF THE NOVI HAN RADIOACTIVE WASTE REPOSITORY. IMPLEMENTATION OF THE EXPERIMENTALLY OBTAINED SORPTION COEFFICIENTS

机译:〜137CS迁移和〜60Co放射核素的型号在Novi Han放射性废物库初步安全评估中的迁移。实验获得的吸附系数的实施

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Studies on the sorption characteristics of radionuclides in geological media are closely related to the safe disposal of radioactive wastes. That is way in the preliminary safety assessment of the near surface repository for low- and intermediate level radioactive waste in Novi Han are implemented an experimentally obtained sorption coefficients ~137Cs and ~60Co. The radionuclide release rates with respect of the preliminary safety assessment are produced too. The mathematical models implemented in the computer code are used for modeling and calculations of the processes connected with the radionuclide migration for the generated leaching scenarios. The scenarios are chosen on the base of analysis and combination of the possible features, events and processes and waste and engineer barrier states as well as the human behavior component. The implementation of the experimentally obtained sorption coefficients for ~l37Cs and ~60Co is a step to obtain the most realistic for the repository site results. The experiments are produced at the laboratories of the Institute using the soil samples from the repository place. A comparison of the transfer results of the indicated above radionuclides using the data from literature sources and experiments are shown and discussed in the paper.
机译:地质介质放射性核素的吸附特性研究与放射性废物的安全处置密切相关。这是在初步安全评估中,对Novi Han的低级和中间水平放射性废物的近地表储存的方式进行了实验获得的吸附系数〜137Cs和〜60Co。也产生了关于初步安全评估的放射性核素释放速率。计算机代码中实现的数学模型用于与所生成的浸出方案的放射核划覆盖迁移连接的进程的建模和计算。这些方案选择在分析基础上,以及可能的功能,事件和过程以及废物和工程障碍状态以及人类行为组件的组合。实验获得的吸附系数的实施对于〜L37CS和〜60Co是获得存储库现场结果最逼真的步骤。实验在研究所的实验室中使用来自储存库的土壤样品来生产。用文献来源和实验中的数据显示和讨论了上述上述放射性核素的转移结果的比较。

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