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Effects of Surface Treatment using Oxide-Dispersion-Strengthening on the Mechanical Properties of Zr-based Fuel Cladding Tubes

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한국재료학회지 (Korean Journal of Materials Research)
한국재료학회 (Materials Research Society Of Korea)
초록

Oxide-dispersion-strengthened (ODS) alloy has been developed to increase the mechanical strength of metallic materials; such an improvement can be realized by distributing fine oxide particles within the material matrix. In this study, the ODS layer was formed in the surface region of Zr-based alloy tubes by laser beam treatment. Two kinds of Zr-based alloys with different alloying elements and microstructures were used: KNF-M (recrystallized) and HANA-6 (partial recrystallized). To form the ODS layer, Y2O3-coated tubes were scanned by a laser beam, which induced penetration of Y2O3 particles into the substrates. The thickness of the ODS layer varied from 20 to 55 μm depending on the laser beam conditions. A heat affected zone developed below the ODS layer; its thickness was larger in the KNF-M alloy than in the HANA-6 alloy. The ring tensile strengths of the KNF-M and HANA-6 alloy samples increased more than two times and 20–50%, respectively. This procedure was effective to increase the strength while maintaining the ductility in the case of the HANA-6 alloy samples; however, an abrupt brittle facture was observed in the KNF-M alloy samples. It is considered that the initial microstructure of the materials affects the formation of ODS and the mechanical behavior.

목차
Abstracts
 1. 서 론
 2. 실험방법
 3. 결과 및 고찰
 4. 결 론
 References
저자
  • 정양일(한국원자력연구원) | Yang-Il Jung (Korea Atomic Energy Research Institute) Corresponding author
  • 김일현(한국원자력연구원) | Il-Hyun Kim (Korea Atomic Energy Research Institute)
  • 김현길(한국원자력연구원) | Hyun-Gil Kim (Korea Atomic Energy Research Institute)
  • 장훈(한전원자력연료) | Hun Jang (KEPCO Nuclear Fuel)
  • 이승재(한전원자력연료) | Seung-Jae Lee (KEPCO Nuclear Fuel)