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首页> 外文期刊>Journal of the Geological Society of India >Radionuclide Transport Mechanism and In Situ Performance, Assessment of Waste Glasses, Metals and Clay Barriers of a Geological Repository: Possible Research Avenues at Puga Geothermal Field, Ladakh, Jammu and Kashmir
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Radionuclide Transport Mechanism and In Situ Performance, Assessment of Waste Glasses, Metals and Clay Barriers of a Geological Repository: Possible Research Avenues at Puga Geothermal Field, Ladakh, Jammu and Kashmir

机译:放射性核素的传输机理和原位性能,地质处置库的废玻璃,金属和粘土屏障的评估:普加地热田,拉达克,查mu和克什米尔的可能研究大道

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摘要

Good analogy in terms of migration of Cs, groundwater chemistry, thermal and hydraulic processes and near field geochemistry, lias been noticed between the Puga Geothermal Field and a typical granite hosted nuclear waste geological repository. The former can contribute immensely for demonstration of long term degradation of material used in geological repository viz. Waste glasses, Backfill and Buffer clays and rocks under the influence of varying thermal-hydraulic and chemical conditions. It also holds good potential to study Cs migration, gas mobility and modification of groundwater chemistry, thereby providing field scale parametric values to a number of key processes of a geological repository for nuclear wastes. The results can be used to validate numerically simulated radionuclide migration pattern through various groundwater pathways.
机译:在Cuga的迁移,地下水化学,热力和水力过程以及近场地球化学方面有很好的类比,在Puga地热田和典型的花岗岩宿主核废料地质处置库之间发现了别名。前者可以为证明地质储藏所使用的材料的长期降解做出巨大贡献。在变化的热工和化学条件的影响下,废玻璃,回填和缓冲粘土和岩石。它还具有研究Cs迁移,气体迁移率和地下水化学变化的良好潜力,从而为核废料地质处置库的许多关键过程提供现场规模的参数值。结果可用于验证通过各种地下水路径进行的数值模拟放射性核素迁移模式。

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