首页> 外文会议>Symposium on Scientific Basis for Nuclear Waste Management; 20061127-1201; Boston,MA(US) >Nuclear Waste Disposal in Deep Geological Formations: What are the Major Remaining Scientific Issues?
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Nuclear Waste Disposal in Deep Geological Formations: What are the Major Remaining Scientific Issues?

机译:深部地质构造中的核废料处置:主要的科学问题是什么?

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For more than thirty years, considerable efforts have been carried out in order to evaluate the possibility of disposing of high level wastes in deep geological formations. Different rock types have been examined, such as water-undersaturated tuffs (USA), granites or crystalline rocks (Canada, Sweden, and Finland), clays (France, Belgium, and Switzerland), rock-salt (Germany). Deep clays and granites, (provided that the most fractured zones are avoided in the second case) are considered to fulfill most allocated functions, either on short term (reversibility) or long term. Chemically reducing conditions favor the immobilization of actinides and most fission products by precipitation, co-precipitation and sorption. If oxidizing conditions prevail, the safety demonstration will mostly rely on the performance of artificial confinement systems. Rock-salt offers limited performance considering the issue of reversibility, which is now perceived as essential, mostly for ethical and sociological reasons. However, several issues would deserve additional research programs, and as a first priority, a clear description of time/space succession of processes during the evolution of the repository. This will allow a better representation of coupled processes in performance assessment, such as the influence of gases (H_2) generated by corrosion, on the long term dynamics of the re-saturation. Geochemical interactions between the host formation and the engineered systems (packages + barriers) are still insufficiently described. Additional gains in performance could be obtained when taking into account processes such as isotopic exchange. Imaginative solutions, employing ceramic- carbon composite materials could be proposed to replace heavy and gas-generating overpacks, or to accommodate the small but probably significant amount of timate> wastes that will be inevitably produced by Generation IV reactor systems.
机译:三十多年来,为了评估在深部地质构造中处置高放废物的可能性,已经进行了相当大的努力。已经检查了不同的岩石类型,例如水不饱和凝灰岩(美国),花岗岩或结晶岩(加拿大,瑞典和芬兰),粘土(法国,比利时和瑞士),盐岩(德国)。深层粘土和花岗岩(假设在第二种情况下避免了最破裂的区域)被认为可以在短期内(可逆性)或长期满足大部分分配的功能。化学还原条件有利于通过沉淀,共沉淀和吸附来固定act系元素和大多数裂变产物。如果存在氧化条件,安全演示将主要依靠人工约束系统的性能。考虑到可逆性问题,岩盐的性能有限,目前人们认为这是必不可少的,主要是出于道德和社会学原因。但是,有几个问题值得额外的研究计划,并且首先要明确描述存储库演化过程中过程的时间/空间连续性。这样可以更好地表示性能评估中的耦合过程,例如腐蚀产生的气体(H_2)对重新饱和的长期动态的影响。主体层和工程系统(包装+屏障)之间的地球化学相互作用仍然不够充分。考虑到同位素交换等过程,可以获得额外的性能提升。可以提出使用陶瓷-碳复合材料的富有想象力的解决方案,以代替沉重的气体产生的外包装,或容纳第四代反应堆系统不可避免地产生的少量但可能大量的“最终”废物。

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