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)
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)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47089547
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COBALT 60; CORROSION PRODUCTS; INCONEL 600; INCONEL 690; INCONEL ALLOYS; OXIDES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STAINLESS STEELS; ZINC
- Descriptors DEC
- ALLOY-NI59CR30FE9; ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON ADDITIONS; CHALCOGENIDES; CHROMIUM ALLOYS; COBALT ISOTOPES; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INCONEL ALLOYS; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IRON ALLOYS; IRON BASE ALLOYS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NUCLEI; ODD-ODD NUCLEI; OXYGEN COMPOUNDS; POWER REACTORS; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format, Folder Name: Poster3(PWR), Paper ID: 10072NPC2014proceedings.pdf; 17 refs., 2 figs.