Models for estimation of service life of concrete barriers in low-level radioactive waste disposal
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. 79 refs., 24 figs., 6 tabs.
- Authors:
-
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Publication Date:
- Research Org.:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Org.:
- USNRC
- OSTI Identifier:
- 6548946
- Report Number(s):
- NUREG/CR-5542; EGG-2597
ON: TI91000576; TRN: 90-033400
- DOE Contract Number:
- AC07-76ID01570
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CONCRETES; DECOMPOSITION; PHYSICAL PROPERTIES; MATHEMATICAL MODELS; LOW-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE DISPOSAL; CALCIUM HYDROXIDES; CORROSION; CRACKING; FLUID FLOW; FREEZING; GEOCHEMISTRY; LEACHING; MASS TRANSFER; SULFATES; THAWING; ALKALINE EARTH METAL COMPOUNDS; BUILDING MATERIALS; CALCIUM COMPOUNDS; CHEMICAL REACTIONS; CHEMISTRY; DISSOLUTION; HYDROGEN COMPOUNDS; HYDROXIDES; MANAGEMENT; MATERIALS; OXYGEN COMPOUNDS; PYROLYSIS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SEPARATION PROCESSES; SULFUR COMPOUNDS; THERMOCHEMICAL PROCESSES; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES; 360604* - Materials- Corrosion, Erosion, & Degradation; 360603 - Materials- Properties; 052002 - Nuclear Fuels- Waste Disposal & Storage
Citation Formats
Walton, J C, Plansky, L E, and Smith, R W. Models for estimation of service life of concrete barriers in low-level radioactive waste disposal. United States: N. p., 1990.
Web. doi:10.2172/6548946.
Walton, J C, Plansky, L E, & Smith, R W. Models for estimation of service life of concrete barriers in low-level radioactive waste disposal. United States. https://doi.org/10.2172/6548946
Walton, J C, Plansky, L E, and Smith, R W. 1990.
"Models for estimation of service life of concrete barriers in low-level radioactive waste disposal". United States. https://doi.org/10.2172/6548946. https://www.osti.gov/servlets/purl/6548946.
@article{osti_6548946,
title = {Models for estimation of service life of concrete barriers in low-level radioactive waste disposal},
author = {Walton, J C and Plansky, L E and Smith, R W},
abstractNote = {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. 79 refs., 24 figs., 6 tabs.},
doi = {10.2172/6548946},
url = {https://www.osti.gov/biblio/6548946},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Sep 01 00:00:00 EDT 1990},
month = {Sat Sep 01 00:00:00 EDT 1990}
}
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