Published October 2014 | Version v1
Miscellaneous

Effect of zinc on corrosion product release behavior under PWR primary system conditions

  • 1. Electric Power Research Institute, Inc. (EPRI), Palo Alto, CA (United States)
  • 2. Dominion Engineering, Inc., Reston, VA (United States)

Description

Testing has been performed by various organizations over time to measure corrosion product release rates in the presence of ppb-levels of dissolved zinc under different PWR primary system chemistry conditions. These conditions include variations in zinc concentration and other coolant chemistry parameters, and testing on oxidized and non-oxidized specimens of various base metals. This paper reports the results of a project to compile and evaluate available data to determine whether sufficient data exist to elucidate the fundamental behavior of zinc with respect to oxide formation, oxide modification and concentration of corrosion products in the coolant as a function of zinc exposure levels and time. This evaluation included laboratory data generated by EDF (e.g., Boreal loop testing), EPRI, Nuclear Steam Supply System vendors and other researchers world-wide (e.g., KHNP/KAERI, Bettis and KAPL laboratories, etc.). Assessments of plant responses to zinc injection were also considered. These included both detailed case studies of the first few plants to inject zinc as well as more global reviews using data collected by EPRI in the PWR Chemistry and Monitoring Assessment (CMA) Database and the Standard Radiation Monitoring Program (SRMP) Database. The outcome of this project included a database and recommendations for further testing needs to more fully elucidate the effect of zinc on corrosion product release behavior. The results are expected to contribute to the development of optimized zinc concentration limits in light of the two main expected benefits of zinc addition (PWSCC mitigation and radiation field mitigation) and the main perceived risk of zinc injection (an increase in corrosion product accumulation on fuel surfaces and thus increased risks of crud induced localized corrosion, CILC, and crud induced power shifts, CIPS). (author)

Part of:
Proceedings of nuclear plant chemistry conference 2014 Sapporo (NPC 2014)

Additional details

Publishing Information

Imprint Title
Proceedings of nuclear plant chemistry conference 2014 Sapporo (NPC 2014)
Imprint Pagination
2471 p.
Journal Page Range
12 p.

Conference

Title
Nuclear plant chemistry conference 2014
Acronym
NPC 2014
Dates
26-31 Oct 2014
Place
Sapporo, Hokkaido (Japan)

Optional Information

Notes
Available as USB Flash Memory Data in PDF format, Folder Name: Poster3(PWR), Paper ID: 10072NPC2014proceedings.pdf; 17 refs., 2 figs.