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Incorporation of “Corrosion-Time” and Effects of Corrosion-Product Spalling in Waste Package Degradation Simulation in the Potential Repository at Yucca Mountain

Published online by Cambridge University Press:  03 September 2012

Joon H. Lee ,
Joel E. Atkins  and
Bryan Dunlap
Joon H. Lee
Affiliation:
INTERA, Inc., CRWMS M&O, 1180 Town Center Drive, Las Vegas, NV 89134, USA
Joel E. Atkins
Affiliation:
INTERA, Inc., CRWMS M&O, 1180 Town Center Drive, Las Vegas, NV 89134, USA
Bryan Dunlap
Affiliation:
INTERA, Inc., CRWMS M&O, 1180 Town Center Drive, Las Vegas, NV 89134, USA
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Abstract

A two-layer waste package (carbon steel outer barrier and Alloy 825 inner barrier) is specified to dispose of high-level nuclear waste at the potential repository at Yucca Mountain. A set of improvements and more realism have been added to a stochastic waste-package degradation model which was developed for a recent total system performance assessment of the potential repository [1]. The waste-package surface is divided into “patches” to better represent the general corrosion of the carbon-steel outer barrier. The “corrosion-time” concept is developed to represent the corrosion of the carbon-steel outer barrier in changing exposure conditions with time such as those expected in the potential repository. With the patches approach and the corrosion-time concept implemented into the waste-package degradation model, sensitivity of the waste package degradation (failure and pitting degradation) to different threshold spalling thicknesses of the corrosion products from the carbon-steel outer barrier is analyzed. The results show that the waste-package pitting degradation is sensitive to the corrosion-products spalling thickness of the carbon-steel outer barrier. A greater pitting degradation of the waste packages is predicted with a smaller spalling thickness. Further understanding of the corrosion-products spalling in different exposure conditions (i.e., water chemistry, water contact mode, etc.) and its effects on carbon steel corrosion is needed to enhance the confidence in the waste-package performance modeling in the potential repository.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 465: Symposium II – Scienfific Basis for Nuclear Waste Management XX , 1996 , 1075
Copyright
Copyright © Materials Research Society 1997

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References

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