Corrosion of Stainless Steel in Simulated Nuclear Reactor Primary Coolant—Experiments and Modeling

Author:

Bojinov Martin1ORCID,Betova Iva2,Karastoyanov Vasil1,Avdeev Georgi3ORCID

Affiliation:

1. Department of Physical Chemistry, University of Chemical Technology and Metallurgy, 1756 Sofia, Bulgaria

2. Institute of Electrochemistry and Energy Systems, Bulgarian Academy of Sciences, 1113 Sofia, Bulgaria

3. Institute of Physical Chemistry, Bulgarian Academy of Sciences, 1113 Sofia, Bulgaria

Abstract

In the present paper, the effect of the evolution of primary water chemistry during power operation on the corrosion rate and conduction mechanism of oxide films on stainless steel is studied by in situ impedance spectroscopy at 300 °C/9 MPa during 1-week exposure periods in an autoclave connected to a recirculation loop. At the end of the exposure period, the samples were anodically polarized in a wide range of potentials to evaluate the stability of the passive oxide. Separate samples of the same steel were simultaneously exposed to the coolant and subsequently analyzed by glow discharge optical emission spectroscopy (GDOES) in order to estimate the thickness and the in-depth composition of the formed oxides. Impedance data were quantitatively interpreted using the mixed-conduction model for oxide films (MCM) to estimate the rates of metal oxidation at the alloy/oxide interface, oxide dissolution and restructuring at the film/coolant interface, and ion transport in the protective corrosion layer.

Funder

European Union-NextGenerationEU through the National Recovery and Resilience Plan of the Republic of Bulgaria

National Scientific Infrastructure “Energy Storage and Hydrogen Energy”

Publisher

MDPI AG

Reference22 articles.

1. McElrath, J. (2014). Pressurized Water Reactor Primary Water Chemistry Guidelines, EPRI.

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3. (2002). Review of VVER Primary Water Chemistry and the Potential for its Use in PWRs: Potassium Hydroxide and/or Ammonia Based Water Chemistries, EPRI.

4. (2015). Feasibility of Using Potassium Hydroxide for Primary Coolant pH Control in Pressurized Water Reactors, EPRI.

5. Fruzzetti, K., Marks, C., Reinders, J., McElrath, J., and Wells, D. (2016, January 2–7). Evaluation of Potassium Hydroxide for Reactor Coolant pHT Control in Western PWRs. Proceedings of the 20th International 15 Conference on Water Chemistry in Nuclear Reactor Systems, Brighton, UK.

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