Site assessment and characterization for high-level nuclear waste disposal; results from the Stripa Project, Sweden

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doi: 10.1144/GSL.QJEGH.1995.028.S1.02
Authors:Olsson, O.; Gale, J. E.
Author Affiliations:Primary:
Conterra AB, Uppsala, Sweden
Other:
Fracflow Consultants, Canada
Volume Title:Quarterly Journal of Engineering Geology
Source:The Quarterly Journal of Engineering Geology, Vol.28(Suppl. 1), p.17-30. Publisher: Scottish Academic Press; Geological Society of London, Edinburgh, United Kingdom. ISSN: 0481-2085
Publication Date:1995
Note:In English. 17 refs.; illus., incl. geol. sketch maps
Summary:The Stripa Project, on geologicaldisposal of radioactive waste, has been completed after a 15-year cooperative international research effort. This article summarizesthe results of research and development on methods to characterize the flow and transport properties of a fractured rock mass for repository site evaluation. The approach used, and the flow and transport experiments conducted, provide new data and permit a comparison ofmodel predictionswith large-scalefieldmeasurements. The 3D discrete fracture models used in this research gave good predictions of flowand transport to sinkscreated by boreholesbut werenot ableadequatelyto representexcavation induced changes to drift inflows.
Subjects:Characterization; Fractures; Models; Numerical models; Radioactive waste; Site exploration; Waste disposal; Europe; Fennoscandian Shield; Orebro Sweden; Scandinavia; Stripa region; Sweden; Western Europe
Abstract Numbers:95M/4180
Record ID:1996010098
Copyright Information:GeoRef, Copyright 2019 American Geosciences Institute.
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