Neutralization of crevice acids. Final report. [PWR]

Technical Report · Sun May 01 04:00:00 EDT 1983

OSTI ID:6062520

Beineke, T A; Grondahl, E E; Orsulak, R M; Hall, J F; Scott, D B; Fink, G C; Silva, E J; Krupowicz, J J; Marugg, K E; Wiatrowski, M

Capsule, pot-boiler, and model steam-generator tests were conducted to develop chemical procedures for limiting dent growth in nuclear steam generators. Testing included isothermal soaks and on-line chemical additions. In the typical test procedure, denting was initiated in the test vehicle, a neutralizer was applied, and the subsequent course of denting followed. Non-destructive and destructive examinations were conducted at the conclusion of testing to investigate the mechanism and side effects of each neutralization procedure. Soak environments included hydraxine-treated water, and solutions of sodium phosphate, sodium nitrite, calcium nitrite, sodium hydroxide, and boric acid. Chemicals used for on-line additions were calcium hydroxide and boric acid.

• Research Organization: Combustion Engineering, Inc., Windsor, CT (USA). Nuclear Power Systems
• OSTI ID: 6062520
• Report Number(s): EPRI-NP-3054; ON: DE83902586
• Country of Publication: United States
• Language: English

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