Corrosion product 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

2 Citations (Scopus)

Abstract

Japanese PWR utilities desire to employ long-term fuel cycle and high bum-up operations. Corrosion product (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) for other utilities. In order to clarify the contribution factors of the deposition, the effects of steaming rate, pHi-, and boron contents in the test solution on the crud deposition were investigated under sub-cooled boiling and non-irradiated condition. From the test results, it was revealed that the spinel oxide layer was formed on the fuel cladding surface in a simulated Japanese PWR fuel cycle chemistry at 325°C. The oxide layer was easily formed on the heated surface of the fuel cladding, and the oxide thickness was increased with increase of steaming rate and decrease of pHT.

Original languageEnglish
Title of host publicationCanadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Pages369-384
Number of pages16
Publication statusPublished - 2007 Dec 1
Externally publishedYes
Event13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 - Whistler, BC, Canada
Duration: 2007 Apr 192007 Apr 23

Publication series

NameCanadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
Volume1

Conference

Conference13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007
CountryCanada
CityWhistler, BC
Period07/4/1907/4/23

Keywords

  • Boric acid concentration
  • Corrosion product
  • Crud
  • PWR primary coolant
  • Zircaloy-4

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality
  • Materials Science(all)

Fingerprint Dive into the research topics of 'Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water'. Together they form a unique fingerprint.

  • Cite this

    Kawamura, H., & Furuya, M. (2007). Corrosion product deposition behavior on heated zircaloy-4 surface in simulated PWR primary water. In Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 (pp. 369-384). (Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007; Vol. 1).