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Transport of gases through concrete barriers. Task 3: Characterization of radioactive waste forms

机译:气体通过混凝土屏障的运输。任务3:放射性废物形态的表征

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摘要

The performance of the cementitious materials within a radioactive waste repository as a physical barrier to the migration of radionuclides depends on the maintenance of the integrity of the barrier. Potentially, this can be compromised by physical damage to the barrier caused by pressurization as gas is generated within the repository. The maintenance of chemical homogeneity within the material used for backfilling the repository may also be compromised as a consequence of gas pressurization through the formation of additional cracks and the reaction of cementitious materials with gases such as carbon dioxide. Consequently, the migration of gas within repository construction materials may be a significant parameter in both the design of a repository and the provision of a safety-case for disposal. The migration of hydrogen, helium, methane, argon and carbon dioxide has been studied for materials selected to be typical of repository structural concretes and grouts that are being considered for backfilling and waste encapsulation. The apparent permeability of these materials to gas has been shown to be dependent on gas type and average pressure in the structural concrete due to the effects of Knudsen flow at pressures of the order of 100 kPa. This is not observed in the grouts due to significantly greater pore size. The permeability coefficients of the grouts are several orders of magnitude greater than those of the concrete. Gas migration is strongly influenced by the degree of water saturation of the materials. The presence of interfaces within the materials results in an increase in permeability at higher degrees of water saturation. A simple model has been developed to simulate the effects of gas pressurization. The tangential hoop stress at the surface of a void is calculated and comparison with the expected tensile strength of the materials is used to assess the potential for cracking. The backfill grouts seem to have sufficient permeability to disperse gas without crack formation.
机译:放射性废物处置库中胶结材料作为放射性核素迁移的物理屏障的性能取决于屏障的完整性。潜在地,这可能是由于在储存库内产生气体而导致的加压对屏障的物理损坏而造成的。由于形成另外的裂缝以及水泥质材料与气体(例如二氧化碳)的反应而导致的气体加压,也可能损害用于回填储存库的材料内化学均质性的维持。因此,储存库建筑材料内的气体迁移可能是储存库设计和提供安全处置箱的重要参数。已经研究了氢气,氦气,甲烷,氩气和二氧化碳的迁移,这些材料被选定为典型的仓库结构混凝土和灌浆材料,这些材料正被考虑用于回填和废物封装。这些材料对气体的表观渗透率已显示出取决于气体类型和结构混凝土中的平均压力,这归因于在压力为100 kPa时的克努森流动。由于明显更大的孔径,在灌浆中未观察到这一点。灌浆的渗透系数比混凝土的渗透系数大几个数量级。气体迁移受材料的水饱和度强烈影响。材料中界面的存在会导致水饱和度更高时渗透率的增加。已开发出一个简单的模型来模拟气体加压的效果。计算空隙表面的切向环向应力,并将其与材料的预期抗拉强度进行比较,以评估产生裂纹的可能性。回填砂浆似乎具有足够的渗透性以分散气体而不会形成裂纹。

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