Author:
Lee Joon H.,Atkins Joel E.,Dunlap Bryan
Abstract
ABSTRACTA 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.
Publisher
Springer Science and Business Media LLC
Cited by
1 articles.
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