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51.
Summary Data on the performance of operating mines in rock salt and potash from United States and British sources is reviewed. A design validation scheme for nuclear waste repositories is proposed, based on back analysis of the response of operating evaporite mines. 相似文献
52.
This study investigates the performance of an optimum compacted bentonite/sand mixture seal for the isolation of underground waste repositories. Engineering geological tests such as compaction, flow, swelling, mechanical and shear strength tests have been conducted to select an optimum mixture and to recommend a stable bentonite/sand seal length-to-radius ratio (L/a) as far as the factor of safety (F) is concerned. The results of the compaction permeameter tests led to a recommendation to select an optimum compacted bentonite/sand mixture possessing a bentonite content of about 20% to satisfy the minimum regulatory hydraulic conductivity requirement. Engineering geological analysis of the seal/rock mechanical interaction with regard to reduce the possibility of seal slip led to a recommendation to utilize a seal L/a of at least 25. 相似文献
53.
To dispose of the spent fuels generated from the Korean nuclear power plants in an underground repository, a large area of
about 4 km2 is required. This could be a constraint for selecting an adequate repository site and it is required to investigate the possibility
of a multi-level repository design. In this study different parameters related to the multi-level repository design such as
the level distance, waste type disposed of at each level, and the time interval between the operations at the levels, were
investigated using the three-dimensional code, FLAC3D. For obtaining more reliable results, rock properties measured from
deep boreholes were used. From the analysis, it was possible to conclude that a multi-level repository concept could be an
attractive alternative to reduce the underground area as well as to dispose of the spent fuels from Pressurized Water Reactors
(PWR) and Canadian Deuterium Uranium (CANDU) reactors at different levels with different time schedules. 相似文献
54.
特别考虑了缓冲层中温度梯度水分扩散、水蒸汽扩散对水连续性及能量守恒的影响，进一步完善了所建立的分析饱和-非饱和介质中热-水-应力耦合现象的控制方程，并针对试验资料，使用所开发的有限元程序对一个核废料处置概念库近场的热-水-应力耦合过程进行了数值模拟，考察了缓冲层及岩体中若干点的温度、饱和度、孔隙水压力及主应力的变化、分布情况，并将部分结果与国外类似软件的计算数据作了对比，结果显示，在定性和定量上二者的规律有某种一致性，从而得出了一定的认识。 相似文献
55.
Peter Blümling 《Geotechnical and Geological Engineering》2005,23(6):843-858
Within the context of the phase IV (1994–1996) research and development activities at the Grimsel Test Site (GTS), Nagra developed, in collaboration with the Agence Nationale pour la Gestion des Déchets Radioactifs (Andra), an investigation project for the sealing of boreholes drilled from underground. The project had the following goals:
The new concept developed in this project was to use highly compacted bentonite pellets only. The two techniques tested were
Both techniques were tested in situ at the GTS to estimate their performance under realistic field conditions. The swelling pressures were monitored for 4 months after seal emplacement until an almost constant value was attained. Finally the hydraulic and mechanical performance of the seal was tested. It was found that the conductivities measured across the seal were equivalent to the matrix properties of the surrounding rock (2–5 × 10−12 m/s). The hydraulic testing also showed no linear preferential flow. 相似文献
| – | sealing of boreholes drilled from underground facilities with a length of up to 500 m, |
| – | sealing of boreholes with mainly irregular shape (e.g. breakouts of borehole wall), |
| – | ensuring a hydraulic conductivity of 10−11–10−12 m/s for the seal, |
| – | ensuring reliable quality control in routine production. |
| (1) | pneumatic injection of pellets into a borehole using a grain size distribution of 4–10 mm, |
| (2) | emplacement using a modified core barrel for transport and compaction of the pellets. |
56.
高放废物处置库新疆雅满苏和天湖预选地段地下水同位素特征及其指示意义 总被引：1，自引：0，他引：1
高放废物地质处置是将高放废物与人类环境安全隔离的有效途径。高放废物处置库的围岩通常为低渗透的岩体,其安全性在很大程度上取决于围岩对核废物的屏障功能和作为核素迁移载体的裂隙水运动特征。因此,开展处置库场址水文地质评价工作尤为重要。新疆雅满苏和天湖预选地段是我国高放废物处置库预选地段之一。花岗岩是选定的围岩。在过去的3年里,为了认识该地段地下水的形成机制和更新能力,提供该区处置库场址筛选和评价的依据,在该区开展了区域水文地质调查和地下水样品采集。根据调查结果和样品测试数据,本文主要讨论了该地段地下水同位素特征及其水文地质意义,结果表明,地下水δ~2H值主要分布在10.6‰至-82.5‰之间,平均值-46.1‰;δ~(18)O值主要分布在10.2‰至-9.8‰‰之间,平均值-2.06‰;地下水氚含量在1TU~46.1TU之间。地下水δ~2H和δ~(18)O散点图显示,二者主要落在大气降水线的附近和下方,表明区内地下水主要源自当地现代降水的补给,并经受了强烈的蒸发作用,且深部地下水交替能力明显弱于浅部地下水。这一认识为该区处置库选址和场址评价提供了重要水文地质依据。 相似文献
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