Understanding the Effects of Zn Injection and OLNC-Treatment on 316 Stainless Steel Oxide under Simulated BWR Conditions

Dora Capone, Ben Spencer, Jonathan Duff, M. Grace Burke, Fabio Scenini, Liberato Volpe, Hideyuki Hosokawa, Yoichi Wada, Tsuyoshi Ito, Makoto Nagase

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

This study investigates the mechanism of incorporation of metal cations (Zn and Co) into the 316 stainless steel (SS) oxide under hydrogenated water chemistry (HWC) and On-Line NobleChemTM (OLNC). Coupons of 316 SS were exposed to simulated boiling water reactor (BWR) conditions (pure water, H:O molar ratio ~8) at 288 °C and then analysed via surface characterisation techniques. Specifically, coupons were initially exposed under HWC conditions for 500 h, then subjected for 200 h to the OLNCtreatment, and then a final exposure under HWC conditions for 500 h, all with simultaneous monitoring of the electrochemical corrosion potential. These exposures were performed both with and without Zn and or Co injection. It was found that Zn decreased the oxide thickness of the inner oxide layer and decreased the size of the crystallites on the outer layer. Addition of 0.2 ppb of Co in the water chemistry containing 10 ppb Zn did not appear to influence the oxide morphology nor its composition. Hard X-ray XPS analysis showed that Zn did not completely suppress Co incorporation in the outer oxide layer which was still found in concentrations up to 0.6 at. % on the surface of the oxide under Zn addition conditions.
Original languageEnglish
Title of host publicationThe 20th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor
Publication statusAccepted/In press - 1 Jul 2022
EventThe 20th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor - , United States
Duration: 17 Jul 202221 Jul 2022

Conference

ConferenceThe 20th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor
Country/TerritoryUnited States
Period17/07/2221/07/22

Research Beacons, Institutes and Platforms

  • Henry Royce Institute

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