Published 2007 | Version v1
Book

Nuclear Waste Disposal in Deep Geological Formations: What are the Major Remaining Scientific Issues?

  • 1. Scientific Direction, INERIS, Parc Technologique ALATA, BP2, Verneuil-en-Halatte, 60550, (France)
  • 2. Institut des Sciences Analytiques, Universite de Lyon, 43 avenue du 11 novembre 1918, Villeurbanne, 69622 (France)

Description

For more than thirty years, considerable efforts have been carried out in order to evaluate the possibility of disposing of high level wastes in deep geological formations. Different rock types have been examined, such as water-under-saturated tuffs (USA), granites or crystalline rocks (Canada, Sweden, and Finland), clays (France, Belgium, and Switzerland), rock-salt (Germany). Deep clays and granites, (provided that the most fractured zones are avoided in the second case) are considered to fulfill most allocated functions, either on short term (reversibility) or long term. Chemically reducing conditions favor the immobilization of actinides and most fission products by precipitation, co-precipitation and sorption. If oxidizing conditions prevail, the safety demonstration will mostly rely on the performance of artificial confinement systems. Rock-salt offers limited performance considering the issue of reversibility, which is now perceived as essential, mostly for ethical and sociological reasons. However, several issues would deserve additional research programs, and as a first priority, a clear description of time/space succession of processes during the evolution of the repository. This will allow a better representation of coupled processes in performance assessment, such as the influence of gases (H2) generated by corrosion, on the long term dynamics of the re-saturation. Geochemical interactions between the host formation and the engineered systems (packages + barriers) are still insufficiently described. Additional gains in performance could be obtained when taking into account processes such as isotopic exchange. Imaginative solutions, employing ceramic- carbon composite materials could be proposed to replace heavy and gas-generating overpacks, or to accommodate the small but probably significant amount of 'ultimate' wastes that will be inevitably produced by Generation IV reactor systems. (author)

Part of:
Proceedings of the symposium on Scientific Basis for Nuclear Waste Management XXX

Additional details

Publishing Information

Publisher
Materials Research Society - MRS
Imprint Place
Warrendale (United States)
ISBN
978-1-55899-942-8
Imprint Title
Proceedings of the symposium on Scientific Basis for Nuclear Waste Management XXX
Imprint Pagination
v. 985, 663 p.
Journal Page Range
p. 219-226
CODEN
MRSPDH

Conference

Title
Symposium on Scientific Basis for Nuclear Waste Management
Dates
27 Nov - 1 Dec 2006
Place
Boston - Massachusetts (United States)

Optional Information

Notes
26 refs.