Published March 1985 | Version v1
Report

Significance of chemical return in nuclear steam generators

  • 1. NWT Corp., San Jose, CA

Description

A reasonable understanding of PWR steam generator corrosion mechanisms such as denting and wastage has been developed, and adequate chemistry control programs defined to obviate the magnitude and effects of these modes of attack. However, relatively unique corrosion attack modes have been encountered at several plants notwithstanding the presence of a reasonable to very good chemistry control program when considered in light of the Steam Generator Owners Group chemistry guidelines. The uniqueness of attack also suggests that parameters not routinely measured or monitored may be playing a significant role. In the authors opinions, the only reasonable method of routinely identifying corrosion accelerating species present in crevices, sludge piles, and deposits in PWR steam generators is by performing detailed chemical return studies during power transients, shutdowns, and long term layups. Although it would be preferable to obtain samples from regions of attack, such samples generally are not available for obvious reasons

Additional details

Publishing Information

Imprint Title
Second EPRI workshop on support-structure corrosion in nuclear plant steam generators: proceedings
Journal Page Range
p. 8.1-8.18.
Report number
EPRI-NP--3924-SR

Conference

Title
2. EPRI workshop on support-structure corrosion in nuclear plant steam generators.
Dates
18-20 Jul 1983.
Place
Seattle, WA (USA).