Corrosion Mechanism and Electrochemical Reactions on Alloy 690 in Simulated Primary Coolant of Water–Water Energy Reactors

Author:

Bojinov Martin1ORCID,Betova Iva2,Karastoyanov Vasil1

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

Abstract

During the power operation of the primary loop of a water cooled–water moderated energy reactor (WWER), the water chemistry evolves from a high-boron high-potassium composition to significantly lower concentrations of both constituents at the end of a campaign, and the Li concentration reaches ca. 0.7–0.9 ppm. In the present paper, the effect of primary water chemistry evolution during operation on the corrosion rate and conduction mechanism of oxides on Alloy 690 is studied by in situ impedance spectroscopy at 300 °C/9 MPa during 1-week exposures in an autoclave connected to a re-circulation loop. At the end of exposure, the samples were anodically polarized at potentials −0.8 to −0.1 V vs. SHE to evaluate the stability of the passive oxide. Simultaneously exposed samples of Alloy 690 were subsequently analyzed by XPS to estimate the thickness and in-depth composition of oxides. Impedance data were quantitatively interpreted using the mixed-conduction model (MCM) for oxide films. The effect of water chemistry evolution on the corrosion rate and conduction mechanism in the oxide on Alloy 690 in a primary coolant is discussed based on the obtained parameters.

Funder

the European Union-NextGenerationEU

the National Scientific Infrastructure “Energy Storage and Hydrogen Energy”

Publisher

MDPI AG

Reference36 articles.

1. (1999). Potassium Hydroxide, A Potential Mitigation for AOA, EPRI. TE-114158.

2. (2002). Review of VVER Primary Water Chemistry and the Potential for its Use in PWRs: Potassium Hydroxide and/or Ammonia Based Water Chemistries, EPRI. TR 1003382.

3. (2015). Feasibility of Using Potassium Hydroxide for Primary Coolant pHT Control in Pressurized Water Reactors, EPRI. 3002005408.

4. Fruzzetti, K., Marks, C., Reinders, J., McElrath, J., and Wells, D.M. (2016, January 2–7). Evaluation of Potassium Hydroxide for Reactor Coolant pHT Control in Western PWRs. Proceedings of the the 20th International Conference on Water Chemistry of Nuclear Reactor Systems, NPC 2016, Brighton, UK. Paper 06.

5. Fruzzetti, K., Demma, A., Chou, P., Smith, J., Hussey, D., Kim, K., Gregorich, C., and Burke, M. (2018, January 9–14). Potassium Hydroxide for PWR Primary Coolant pH Control: Qualification Program. Proceedings of the 21st International Conference on Water Chemistry of Nuclear Reactor Systems, NPC 2018, San Francisco, CA, USA. Poster 11B.

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