논문 상세보기

Analysis of Crud on Thick Oxide Layer Formed on Zirconium Alloy Cladding

  • 언어ENG
  • URLhttps://db.koreascholar.com/Article/Detail/431043
모든 회원에게 무료로 제공됩니다.
한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

It has been known that as oxide layer (ZrO2) forms on the nuclear fuel cladding during irradiation in nuclear power plants, the corrosion kinetics are influenced by various parameters such as chemical environments. One of those environments, crud deposition driven by coolant chemistry has an adverse effect on the formation of oxide (ZrO2) and leads to increase thickness of the layer. In this study, crud formation was performed through loop experiment equipment on the surface of intentionally-made oxide layer (ZrO2) on cladding tubes and then the composition and characteristics of cruds were examined for the investigation of nuclear power plant environment. As a result, various cruds in composition and microstructure were formed depending on the exquisite methods and conditions such as metal ion concentration.

저자
  • Joo Young Park(KEPCO Nuclear Fuel (KEPCO NF)) corresponding author
  • Kyung Tae Kim(KEPCO Nuclear Fuel (KEPCO NF))
  • Jeong Won Kim(KEPCO Nuclear Fuel (KEPCO NF))
  • Oh Hyun Kwon(KEPCO Nuclear Fuel (KEPCO NF))