Published 2005 | Version v1
Miscellaneous

Diffusion of humic colloids in compacted bentonite

  • 1. Royal Institute of Technology, Dpt. of Chemistry / Nuclear Chemistry, Stockholm (Sweden)

Description

In Sweden, as in many other countries, compacted bentonite will surround the encapsulated spent nuclear fuel in a deep bedrock repository. Bentonite gives mechanical support and minimizes the water flow over the deposition holes. The retardation for cationic radionuclides escaping a faulted canister is high in saturated compacted bentonite, since cationic radionuclides sorbs strongly on the bentonite surface, and the only plausible transport mechanism is diffusion. Sorption and diffusion of radionuclides in the bentonite barrier has been extensively studied, and sorption and diffusion coefficients are well established. There is a lack of knowledge as well as data for effects of colloids on radionuclide mobility and transport in the bentonite barrier. In a deep bedrock repository, colloids, particles in the size range of 1-1000 nm, will be present, however in very low concentrations. The colloids origin from eroded bedrock and filling material, mineral oxides, clay, degraded organic compounds and micro-organisms etc. The bentonite barrier is regarded to be an efficient filtering barrier for colloids. With the widely spread micro-structure with pores in between the montmorillonite flakes in the size range of nm, and the inter particle voids partly gel filled of sizes, colloid transport seems unlikely. In a Japanese diffusion study on gold colloids no breakthrough of the colloids was detected. However, to reject the possibility of enhancement of transport of radionuclides by colloids, more data from diffusion studies on other types of colloids in compacted bentonite are needed. Therefore diffusion experiments of Humic Colloids (HC), in the size range of 1-10 nm, were performed. (author)

Part of:
Clays in natural and engineered barriers for radioactive waste confinement

Additional details

Publishing Information

Imprint Title
Clays in natural and engineered barriers for radioactive waste confinement
Imprint Pagination
723 p.
Journal Page Range
p. 476-477
Report number
INIS-FR--3949

Conference

Title
2. international meeting clays in natural and engineered barriers for radioactive waste confinement
Dates
14-18 Mar 2005
Place
Tours (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
37018341
Subject category
S58: GEOSCIENCES;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENTONITE; COLLOIDS; DIFFUSION; RADIOACTIVE WASTE DISPOSAL; RADIONUCLIDE MIGRATION; SORPTION
Descriptors DEC
CLAYS; DISPERSIONS; ENVIRONMENTAL TRANSPORT; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; MANAGEMENT; MASS TRANSFER; MATERIALS; MINERALS; RADIOACTIVE WASTE MANAGEMENT; SILICATE MINERALS; WASTE DISPOSAL; WASTE MANAGEMENT

Optional Information