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Safety Assessment of Geological Disposal of High-Level Radioactive Waste in Boom Clay: Relation With the Radionuclide Inventory

[+] Author Affiliations
Pierre Van Iseghem, Jan Marivoet

SCK-CEN, Mol, Belgium

Paper No. ICEM2009-16418, pp. 617-622; 6 pages
doi:10.1115/ICEM2009-16418
From:
  • ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management
  • ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management, Volume 1
  • Liverpool, UK, October 11–15, 2009
  • Conference Sponsors: Nuclear Engineering Division and Environmental Engineering Division
  • ISBN: 978-0-7918-4407-6 | eISBN: 978-0-7918-3865-X
  • Copyright © 2009 by ASME

abstract

This paper discusses the impact of the parameter values used for the transport of radionuclides from high-level radioactive waste to the far-field on the long-term safety of a proposed geological disposal in the Boom Clay formation in Belgium. The methodology of the Safety Assessment is explained, and the results of the Safety Assessment for vitrified high-level waste and spent fuel are presented. The radionuclides having the strongest impact on the dose-to-man for both HLW glass and spent fuel are 79 Se, 129 I, 126 Sn, 36 Cl, and 99 Tc. Some of them are volatile during the vitrification process, other radionuclides are activation products, and for many of them there is no accurate information on their inventory in the waste form. The hypotheses in the selection of the main parameter values are further discussed, together with the status of the R&D on one of the main dose contributing radionuclides (79 Se).

Copyright © 2009 by ASME

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