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Corrosion models for predictions of performance of high-level radioactive-waste containers
Author(s) -
Jane Farmer,
R.D. McCright,
G.E. Gdowski
Publication year - 1991
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/138267
Subject(s) - radioactive waste , corrosion , high level waste , spent nuclear fuel , stress corrosion cracking , container (type theory) , environmental science , degradation (telecommunications) , metallurgy , waste management , materials science , engineering , composite material , telecommunications
The present plan for disposal of high-level radioactive waste in the US is to seal it in containers before emplacement in a geologic repository. A proposed site at Yucca Mountain, Nevada, is being evaluated for its suitability as a geologic repository. The containers will probably be made of either an austenitic or a copper-based alloy. Models of alloy degradation are being used to predict the long-term performance of the containers under repository conditions. The models are of uniform oxidation and corrosion, localized corrosion, and stress corrosion cracking, and are applicable to worst-case scenarios of container degradation. This paper reviews several of the models

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