Corrosion of single layer thin film protective coatings on steel substrates for high level waste containers
- 1. Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695-7909 (United States)
- 2. Nuclear Engineering Program, University of Florida, Gainesville, FL 32611 (United States)
Description
Highlights: •Measured uniform and localized corrosion for bare and singly-coated steel substrates. •Calculated activation parameters for macroscale corrosion and passive breakdown. •Corrosion in circulating salt brines over extended period is negligible. -- Abstract: Single-layer thin film coatings have been deposited on steel substrates and tested for their corrosion resistance. These coatings include TiN, ZrO2, TiO2, Al2O3, and MoS2, and it is proposed that they will act as barriers to provide protection to the steel canisters that are part of the dry cask storage system for high level nuclear waste. Corrosion testing was completed using electrochemical potentiodynamic polarization techniques in aerated 1 M NaCl solution. Results show an exponential increase in corrosion rate with increasing temperature and an exponential decrease in the passive breakdown overpotential, which is directly related to the ability of a material to form and sustain a corrosion-inhibiting passive film in a given environment. Additionally, kinetic activation parameters have been experimentally determined for each material, leading to predictive equations for corrosion rates. The bare and coated samples corrode analogously, indicative of pores allowing the coating and substrate to corrode simultaneously. The samples were also placed in circulating salt brines of varying pH as a supplementary corrosion testing mechanism to explore their corrosivity over extended time. Negligible weight change was experienced by the bare and coated steel samples over a period of 5 months. Increasing the coating thickness and the number of layers may provide higher resistance to uniform and localized corrosion.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2016.02.016Additional details
Additional titles
- Augmented title (English)
- Spent nuclear fuel;Nuclear waste canister;Dry cask storage;Electrochemical corrosion;Corrosion;Thin film coatings;Passivity;Activation
Identifiers
- DOI
- 10.1016/j.pnucene.2016.02.016;
- PII
- S0149197016300385;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 89
- Journal Page Range
- p. 159-169
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51027708
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ALUMINIUM OXIDES; CORROSION RESISTANCE; DRY STORAGE; ELECTROCHEMICAL CORROSION; ELECTROCHEMISTRY; HIGH-LEVEL RADIOACTIVE WASTES; MOLYBDENUM SULFIDES; OXIDATION; PASSIVITY; PREDICTION EQUATIONS; PROTECTIVE COATINGS; SODIUM CHLORIDES; SPENT FUELS; STEELS; SUBSTRATES; TESTING; THIN FILMS; TITANIUM OXIDES; ZIRCONIUM OXIDES
- Descriptors DEC
- ALKALI METAL COMPOUNDS; ALLOYS; ALUMINIUM COMPOUNDS; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL REACTIONS; CHEMISTRY; CHLORIDES; CHLORINE COMPOUNDS; COATINGS; CORROSION; ENERGY SOURCES; EQUATIONS; FILMS; FUELS; HALIDES; HALOGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MOLYBDENUM COMPOUNDS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR MATERIALS; REFRACTORY METAL COMPOUNDS; SODIUM COMPOUNDS; SODIUM HALIDES; STORAGE; SULFIDES; SULFUR COMPOUNDS; TITANIUM COMPOUNDS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; WASTES; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- Copyright © 2016 Elsevier Ltd. All rights reserved.