Published 2005 | Version v1
Miscellaneous

Dissolution kinetics of smectite under alkaline conditions

  • 1. Kanazawa Univ., Institute of Nature and Environmental Technology, Kanazawa, Ishikawa (Japan)
  • 2. Kanazawa Univ., Graduate School of Natural Science and Technology, Kanazawa, Ishikawa (Japan)
  • 3. Johns Hopkins Univ., Dept. of Earth and Planetary Sciences, Baltimore, M D (United States)
  • 4. Japan Atomic Energy Research Institute, Dept. of Fuel Cycle Safety Research, Tokai, Ibaraki (Japan)

Description

Extensive use of cement for encapsulation, backfilling, and grouting purposes is envisaged in radioactive waste disposal. Degradation of cement materials through contact with groundwater can produce a high pH pore fluid initially ranging from pH 13.0 to 13.5. The pore fluid pH eventually decreases to moderately alkaline ranges due to formation and evolution of subsequent materials. The high pH pore fluids can migrate outwards where it will chemically react with the host rock, and the bentonite utilized to enhance the repository's integrity. These chemical reactions degrade the host rocks' and bentonite ability to absorb radionuclides. Smectites comprising the bulk of bentonite can lose some of their desirable properties during the early stages of bentonite-cement-pore fluid interaction. This has been a key research issue in the performance assessment of radioactive waste disposal system. Elucidating the effects of high pH pore fluid on the physical and chemical properties of smectites (i.e. especially dissolution behavior and rates) is of utmost importance. Stirred-flow-through dissolution experiments were utilized to derive reliable dissolution rates for smectites under neutral to highly alkaline conditions. The effects of pH and temperature on smectite dissolution rates were also investigated. (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. 15-16
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
37018108
Subject category
S58: GEOSCIENCES; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BACKFILLING; DISSOLUTION; HYDROTHERMAL ALTERATION; PH VALUE; RADIOACTIVE WASTE DISPOSAL; ROCK-FLUID INTERACTIONS; SMECTITE; TEMPERATURE DEPENDENCE; WASTE-ROCK INTERACTIONS
Descriptors DEC
CLAYS; MANAGEMENT; METAMORPHISM; MINERALS; RADIOACTIVE WASTE MANAGEMENT; SILICATE MINERALS; WASTE DISPOSAL; WASTE MANAGEMENT

Optional Information