Effect of Ni/Fe ratio and Ni concentration on crud deposition behavior on heated zircaloy-4 surface in simulated pwr primary water

Hirotaka Kawamura, Masahiro Furuya

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Abstract

Crud deposition on fuel cladding surface would become significant issue in Japanese PWRs, because the large amounts of crud deposition has led to an increase of the dose rate in the primary coolant system and become a root cause of axial offset anomalies (AOA). In order to clarify the contribution factors of the deposition, the effects of heat flux, Ni/Fe ratio and nickel concentration in the test solution on the crud deposition were investigated in a simulated Japanese PWR fuel cycle chemistry at 325°C under sub-cooled boiling and non-irradiated condition. From the test results, it was revealed that the crud layer composed of NiFe2O4 and NiO was formed on the fuel cladding. The amounts of deposited crud layer increased with increase of heat flux and Ni/Fe ratio in the test solution. Ni contents in the crud layer increased with increase of Ni concentration in the test solution.

Original languageEnglish
Title of host publication14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Pages1124-1135
Number of pages12
Publication statusPublished - 2009 Dec 1
Externally publishedYes
Event714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 - Virginia Beach, VA, United States
Duration: 2009 Aug 232009 Aug 27

Publication series

Name14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Volume2

Conference

Conference714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
CountryUnited States
CityVirginia Beach, VA
Period09/8/2309/8/27

Keywords

  • Corrosion product
  • Crud
  • Ni/Fe ratio
  • Nickel concentration
  • PWR primary coolant
  • Zircaloy-4

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Environmental Engineering

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