The Status of the Site Characterization and Validation Program in Phase III of the OECD/NEA Stripa Project

by Paul Gnirk,
Bengt Stillborg,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1990

Abstract: In 1980, the International Stripa Project was organized under the aegis of the OECD Nuclear Energy Agency for the purpose of conducting research, at the Stripa mine in Sweden, related to the disposal of high-level radioactive waste in geologic media. Since its inception in 1980, the Stripa Project has evolved into three phases, with Phase III being initiated in 1986. During Phases I and II, the principal emphasis of the research activities was placed on the development of tools and techniques for site characterization and for backfilling and sealing underground excavations, as well as obtaining a fundamental understanding of the nuclide-migration process in fractured rock masses. One of the principal objectives of Phase III is to integrate the various site characterization techniques and methods of analysis for the prediction of ground-water flow and nuclide transport in a previously unexplored volume of granite in the Stripa mine. The activities to accomplish this objective are being carried out under the auspices of the site characterization and validation (SCV) program. The rationale and details of the five stages of the SCV program are discussed, along with the results that have been obtained to date by the characterization techniques and the ground-water flow modelling.

Subject Headings: Project management | Validation | Groundwater flow | Radioactive wastes | Site investigation | Rock masses | Mines and mining | Nuclear power | Europe | Sweden

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