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Test Sorption on Concrete Samples

[+] Author Affiliations
Mirela Olteanu, Crina Bucur

Institute for Nuclear Research, Moscow, Russia

Paper No. ICEM2003-4738, pp. 1341-1343; 3 pages
  • ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
  • 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3
  • Oxford, England, September 21–25, 2003
  • Conference Sponsors: Nuclear Engineering Division and Environmental Engineering Division
  • ISBN: 0-7918-3732-7 | eISBN: 0-7918-3731-9
  • Copyright © 2003 by ASME


The near-field disposal facility will be design to provide effective containment for the radionuclide in the waste. Its design is based on a concept of multi-barrier containment, which makes use of physical (by the steel and concrete packaging) and chemical containment (based on development of uniform, beneficial aqueous condition and the provision of a high sorption capacity across the repository) within the cell of repository and of geological isolation. The achieve of this paper is to evaluate the chemical containment process (sorption capacity of backfill, distribution coefficient) of the potential contaminants which can be releases from radioactive waste conditioned form disposed in this repository, because of the dissolution/leaching processes.

Copyright © 2003 by ASME
Topics: Concretes , Sorption



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