Determination and verification of required water chemistry limits. Volume 1. Summary report. Final report. [PWR]

Technical Report · Thu Mar 01 04:00:00 EST 1984

OSTI ID:6905962

Klisiewicz, J W; Wiatrowski, M; Helyer, M H; Marugg, K E; Patel, B M; Sireci, J E

Isothermal and heat transfer tests were employed to address the concerns of steam generator tube denting, particularly those conditions involved with the initiation of the denting process. Isothermal tests were used to establish relationships between dissolved condenser cooling-water species, tube denting, and associated corrosion morphology. Two low-heat-flux pot boiler tests were conducted to identify potential corrosion concerns of long term low-level condenser inleakage of seawater and of pH-adjusted fresh water (simulating cooling-tower operation). Two moderate-heat-flux model boiler tests were performed to evaluate the role of bulk water chloride and its effect on tube denting. The first test operated for 272 days, and NPM resulted in tube denting and subsequent support-plate cracking observed on the carbon steel drilled support plate. Tube denting was not observed at ferritic stainless steel support systems. The second test operated for 530 steaming days. Carbon steel drilled support-plate ligament cracking was observed after 52.3 ppM chloride days. During this test there was no evidence of accelerated corrosion of the ferritic stainless steel support systems and carbon steel eggcrate support systems.

• Research Organization: Combustion Engineering, Inc., Windsor, CT (USA). Nuclear Power Systems
• OSTI ID: 6905962
• Report Number(s): EPRI-NP-3274-Vol.1; ON: TI84920312
• Country of Publication: United States
• Language: English

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