Published February 1989 | Version v1
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The long-term prediction of corrosion of stainless steel nuclear waste canisters

  • 1. UKAEA Harwell Lab. (UK). Theoretical Physics Div.

Description

In this paper, we describe the preliminary stages of the development of a mathematical model of the evolution of the solution chemistry within a corroding crevice on passive stainless steel. It is based on a formulation by Oldfield and Sutton (1), but models the physical and chemical processes which determine the crevice solution in a more rigorous manner. The model will eventually be used to assess whether a 'critical solution composition', which results in the depassivation of the crevice and the onset of localised corrosion, is attainable for a range of repository conditions, steel types and canister designs etc. We also describe experiments that provide input data in the form of passive currents for this model. Preliminary sensitivity tests with the model have indicated a need for accurate thermodynamic data for the chemical equilibria constants (particularly those for the chromium reactions). These tests also suggest that there are certain critical relationships between various parameters in the system (such as crevice dimensions, the composition of solution outside the crevice and the passive current) that mark different behaviour in the evolution of the solution composition. Further experiments are required both to validate the predictions of the model and to determine whether the predicted compositions of the crevice solutions are sufficiently aggressive to initiate crevice corrosion. (author)

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Additional details

Publishing Information

Imprint Pagination
16 p.
Report number
NSS-R--136

Conference

Title
MRS symposium on the scientific basis for nuclear waste management.
Dates
10-13 Oct 1988.
Place
Berlin (Germany, F.R.).

INIS

Optional Information

Secondary number(s)
DOE-RW--89/007.