Models for Estimation of Service Life of Concrete Barriers in Low-Level Radioactive Waste Disposal (NUREG/CR-5542, EGG-2597)

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Publication Information

Manuscript Completed: July 1990
Date Published: September 1990

Prepared by:
J. C. Walton, L. E. Plansky, R. W. Smith

Idaho National Engineering Laboratory
Managed by the U.S. Department or Energy

EG&G Idaho, Inc.
P.O. Box 1625
Idaho Falls, ID 83415

Prepared for:
Division of Engineering
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555
NRC FIN A6858

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Abstract

Concrete barriers will be used as intimate parts of systems for isolation of low-level radioactive wastes subsequent to disposal. This work reviews mathematical models for estimating the degradation rate of concrete in typical service environments. The models considered cover sulfate attack, reinforcement corrosion, calcium hydroxide leaching, carbonation, freeze/thaw, and cracking. Additionally, fluid flow, mass transport, and geochemical properties of concrete are briefly reviewed. Example calculations included illustrate the types of predictions expected of the models.