Published September 2014 | Version v1
Miscellaneous

Electrochemical corrosion of zircaloys under irradiation and different water chemistry conditions

  • 1. GE Global Research Center, Schenectady, NY (United States)
  • 2. Electric Power Research Institute, Palo Alto, CA (United States)
  • 3. Department of Physics, Illinois Institute of Technology, Chicago, IL (United States)

Description

Shadow corrosion is observed in BWRs either on fuel cladding in contact with Inconel spacers or on channel in close proximity to 304 SS control blades. In order to understand the shadow corrosion mechanism, electrochemical corrosion behavior of Zircaloy-2, Alloy X-750 and 304 SS were previously investigated under UV radiation and published previously. In this study, effects of radiation (up to 300 keV photons) and water chemistry on the electrochemical corrosion behavior of Zircaloy-2, Alloy X-750, and 304 SS were investigated. Measurements of corrosion potential, galvanic corrosion and electrochemical impedance were carried out in 0.01M Na2SO4 at 25degC under UV illumination at 5 eV or photon energies from 2.5 keV to 300 keV using synchrotron radiation. Also, similar measurements were performed in high purity water under various water chemistry conditions at 290degC - 300degC by using UV illumination. The results show that the presence of radiation shifted the corrosion potential of Zircaloy-2 and Alloy X-750 in the anodic or cathodic direction, respectively, and increased anodic currents when Zircaloy-2 was galvanically coupled with Alloy X-750 in 0.01M Na2SO4 at 25degC, may cause accelerated corrosion of Zircaloy-2. In addition, the results showed that hydrogen peroxide increased the electrochemical kinetics at Zircaloy-2 surface in high temperature water under UV irradiation. (author)

Part of:
Proceedings of 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting (WRFPM 2014)

Additional details

Publishing Information

Imprint Title
Proceedings of 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting (WRFPM 2014)
Imprint Pagination
784 p.
Journal Page Range
7 p.

Conference

Title
2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting
Acronym
WRFPM 2014
Dates
14-17 Sep 2014
Place
Sendai, Miyagi (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
47070635
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; ELECTROCHEMICAL CORROSION; FUEL CANS; HYDROGEN PEROXIDE; INCONEL X750; KEV RANGE; RADIATION EFFECTS; REACTOR COOLING SYSTEMS; STAINLESS STEEL-304; SYNCHROTRON RADIATION; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K; ULTRAVIOLET RADIATION; WATER CHEMISTRY; X RADIATION; ZIRCALOY 2
Descriptors DEC
ALLOY-NI73CR15FE7TI3; ALLOYS; ALLOY-ZR98SN-2; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; AUSTENITIC STEELS; BREMSSTRAHLUNG; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; ELECTROMAGNETIC RADIATION; ENERGY RANGE; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; INCONEL ALLOYS; IONIZING RADIATIONS; IRON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NICKEL ADDITIONS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ADDITIONS; NIOBIUM ALLOYS; OXYGEN COMPOUNDS; PEROXIDES; POWER REACTORS; RADIATIONS; REACTOR COMPONENTS; REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; TIN ALLOYS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Notes
Available as CD-ROM Data in PDF format, Paper ID: fullpaper100030.pdf; 14 refs., 15 figs.