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Water corrosion and release mechanism of cement matrix incorporating simulated medium-level waste

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5321114

Previous works on cement leached in water and containing radioactive wastes like cesium and strontium agree to attribute the release in the liquid phase to a diffusion mechanism. The kinetic release can be represented by an empirical relationship in which the dependence of the leached fraction Fr = C/C/sub o/ versus time t assumes the form Fr = Bt/sup n/ and the factor n = 0.5 is typical of a diffusion process. On the other hand, the results of the authors' studies on cement leached in static water demonstrate that the release of calcium, considered to be representative of matrix degradation, follows a time dependence of t/sup 0.25/. A model is suggested for which the release of calcium depends on superposition of two processes: a diffusion through a reaction layer of calcium silicate hydrate around the cement particles during the hydration step and a diffusion of elements from the bulk of cement toward the external surface of the specimen. Based on this schematic diffusion mechanism, some suggestions are advanced to improve the physical characteristics and to increase the retention of the radioactive waste encapsulated in the cement matrix.

Research Organization:
Commission of the European Communities, Joint Research Centre-Ispra Establishment, 21020 Ispra (Va) (IT)
OSTI ID:
5321114
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 77:3; ISSN NUTYB
Country of Publication:
United States
Language:
English

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