Efficacy of argillaceous minerals used as a migration barrier in a geological waste repository
Creators
- 1. Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Chemische Technologie der Nuklearen Entsorgung
Description
The current strategy for isolating nuclear wastes in an underground geological repository relies on a series of multiple barriers to restrict the release of radionuclides to the biosphere. Waste form and canister as well as the backfill material used to fill the space between the waste canister and the host rock, provide engineered barriers, whereas the repository itself and the overlying geologic medium represent natural barriers. A suitable backfill material, preferentially argillaceous minerals, exhibits the potential for providing a multifunctional role in the overall performance of the waste package, significantly retarding radionuclide migration via solution flow. The backfill barrier will serve both as a physical barrier, preventing convective solution flow and allowing radionuclide penetration only by diffusion, and as a chemical barrier capable of chemically interacting with the radionuclides via sorption, ion exchange or precipitation. The paper presents measurements of the hydraulic properties and the diffusion and sorption abilities of various bentonites and clays. They include investigations dealing with the sorption and retardation behaviour of the two most important fission product radionuclides, strontium and cesium. The Ksub(d)-values determined by batch distribution measurements show a strong dependence from the salt concentration in the solutions. Brine solutions bring about a displacement action upon sorbed ions. In highly compacted bentonites the transport of radionuclides through the backfill may be dominated by diffusion through the interstitial water. The rate of diffusion will thus depend on normal diffusion and on the sorption properties of the clay minerals. (author)
Additional details
Publishing Information
- Imprint Title
- Inorganic ion exchangers and adsorbents for chemical processing in the nuclear fuel cycle
- Imprint Pagination
- 282 p.
- Journal Page Range
- p. 143-156.
- Report number
- IAEA-TECDOC--337
Conference
- Title
- Technical committee meeting on inorganic ion exchangers and adsorbents for chemical processing in the nuclear fuel cycle.
- Dates
- 12-15 Jun 1984.
- Place
- Vienna (Austria).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 16078441
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ADSORPTION ISOTHERMS; AQUEOUS SOLUTIONS; BENTONITE; CESIUM COMPOUNDS; CHEMICAL COMPOSITION; CLAYS; DIFFUSION; DISTRIBUTION FUNCTIONS; EQUILIBRIUM; EXPERIMENTAL DATA; HYDRAULIC CONDUCTIVITY; RADIOACTIVE WASTE DISPOSAL; RADIONUCLIDE MIGRATION; STRONTIUM COMPOUNDS; TIME DEPENDENCE; UNDERGROUND DISPOSAL
- Descriptors DEC
- ALKALI METAL COMPOUNDS; ALKALINE EARTH METAL COMPOUNDS; DATA; DISPERSIONS; ENVIRONMENTAL TRANSPORT; HOMOGENEOUS MIXTURES; INFORMATION; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; MANAGEMENT; MASS TRANSFER; MATERIALS; MINERALS; MIXTURES; NUMERICAL DATA; SILICATE MINERALS; SOLUTIONS; WASTE DISPOSAL; WASTE MANAGEMENT