Surface treatment to form a dispersed Y2O3 layer on Zircaloy-4 tubes

被引:12
作者
Jung, Yang-Il [1 ]
Kim, Hyun-Gil [1 ]
Guim, Hwan-Uk [2 ]
Lim, Yoon-Soo [3 ]
Park, Jung-Hwan [1 ]
Park, Dong-Jun [1 ]
Yang, Jae-Ho [1 ]
机构
[1] Korea Atom Energy Res Inst, LWR Fuel Technol Div, Daejeon 34057, South Korea
[2] Korea Basic Sci Inst, Ctr Electron Microscopy Res, Daejeon 34133, South Korea
[3] Hanbat Natl Univ, Dept Adv Mat Engn, Daejeon 34158, South Korea
基金
新加坡国家研究基金会;
关键词
Zirconium alloy; Oxide-dispersion-strengthened (ODS) alloy; Laser surface treatment; Microstructure development; FUEL; MICROSTRUCTURE; ZIRCONIUM; ALLOYS; STEEL;
D O I
10.1016/j.apsusc.2017.06.108
中图分类号
O64 [物理化学(理论化学)、化学物理学];
学科分类号
070304 ; 081704 ;
摘要
Zircaloy-4 is a traditional zirconium-based alloy developed for application in nuclear fuel cladding tubes. The surfaces of Zircaloy-4 tubes were treated using a laser beam to increase their mechanical strength. Laser beam scanning of a tube coated with yttrium oxide (Y2O3) resulted in the formation of a dispersed oxide layer in the tube's surface region. Y2O3 particles penetrated the Zircaloy-4 during the laser treatment and were distributed uniformly in the surface region. The thickness of the dispersed oxide layer varied from 50 to 140 pin depending on the laser beam trajectory. The laser treatment also modified the texture of the tube. The preferred basal orientation along the normal to the tube surface disappeared, and a random structure appeared after laser processing. The most obvious result was an increase in the mechanical strength. The tensile strength of Zircaloy-4 increased by 10-20% with the formation of the dispersed oxide layer. The compressive yield stress also increased, by more than 15%. Brittle fracture was observed in the surface-treated samples during tensile and compressive deformation at room temperature; however, the fracture behavior was changed in ductile at elevated temperatures. (C) 2017 Elsevier B.V. All rights reserved.
引用
收藏
页码:272 / 277
页数:6
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