Review of the Modelling of Corrosion Processes and Lifetime Prediction for HLW/SF Containers—Part 1: Process Models

Author:

King Fraser1ORCID,Kolàř Miroslav2ORCID,Briggs Scott3ORCID,Behazin Mehran3ORCID,Keech Peter3,Diomidis Nikitas4ORCID

Affiliation:

1. Integrity Corrosion Consulting Ltd., Nanaimo, BC V9T 1K2, Canada

2. LS Computing Ltd., Elkford, BC V0B 1H0, Canada

3. Nuclear Waste Management Organization, Toronto, ON M4T 2S3, Canada

4. Nagra, CH-5430 Wettingen, Switzerland

Abstract

The disposal of high-level radioactive waste (HLW) and spent nuclear fuel (SF) presents a unique challenge for the prediction of the long-term performance of corrodible structures since HLW/SF containers are expected, in some cases, to have lifetimes of one million years or longer. Various empirical and deterministic models have been developed over the past 45 years for making predictions of long-term corrosion behaviour, including models for uniform and localised corrosion, environmentally assisted cracking, microbiologically influenced corrosion, and radiation-induced corrosion. More recently, fracture-mechanics-based approaches have been developed to account for joint mechanical–corrosion degradation modes. Regardless of whether empirical or deterministic models are used, it is essential to be able to demonstrate a thorough mechanistic understanding of the corrosion processes involved. In addition to process models focused on specific corrosion mechanisms, there is also a need for performance-assessment models as part of the overall demonstration of the safety of a deep geological repository. Performance-assessment models are discussed in Part 2 of this review.

Publisher

MDPI AG

Reference300 articles.

1. Posiva (2021). Canister Evolution, Posiva Oy. Working Report WR-2021-06.

2. Ondraf/Niras (2004). A Review of Corrosion and Material Selection Issues Pertinent to Underground Disposal of Highly Active Nuclear Waste in Belgium: A Report for ONDRAF/NIRAS Prepared by the Corrosion Study Panel, Ondraf-Niras. Technical Report NIROND 2004-02.

3. Swedish Corrosion Institute (1978). Copper as Canister Material for Unreprocessed Nuclear Waste—Evaluation with Respect to Corrosion, Kärnbränslesäkerhet. Technical Report KBS TR-90.

4. Swedish Corrosion Institute (1983). Corrosion Resistance of a Copper Canister for Spent Fuel, Kärnbränsleförsörjning AB/Avdelning KBS. Technical Report KBS 83-24.

5. An assessment of carbon steel containers for radioactive waste disposal;Marsh;Corros. Sci.,1988

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