Effect of a surface oxide-dispersion-strengthened layer on mechanical strength of zircaloy-4 tubes

被引:5
作者
Jung, Yang-Il [1 ]
Park, Dong-Jun [1 ]
Park, Jung-Hwan [1 ]
Kim, Hyun-Gil [1 ]
Yang, Jae-Ho [1 ]
Koo, Yang-Hyun [1 ]
机构
[1] Korea Atom Energy Res Inst, Nucl Fuel Safety Res Div, Daejeon 34057, South Korea
基金
新加坡国家研究基金会;
关键词
Laser Surface Treatment; Microstructure; Oxide Dispersion Strengthened Alloy; Tensile Strength; Zirconium Alloy; ZIRCONIUM; BEHAVIOR; FUEL;
D O I
10.1016/j.net.2017.12.001
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
An oxide-dispersion-strengthened (ODS) layer was formed on Zircaloy-4 tubes by a laser beam scanning process to increase mechanical strength. Laser beam was used to scan the yttrium oxide (Y2O3)-ecoated Zircaloy-4 tube to induce the penetration of Y2O3 particles into Zircaloy-4. Laser surface treatment resulted in the formation of an ODS layer as well as microstructural phase transformation at the surface of the tube. The mechanical strength of Zircaloy-4 increased with the formation of the ODS layer. The ring-tensile strength of Zircaloy-4 increased from 790 to 870 MPa at room temperature, from 500 to 575 MPa at 380 degrees C, and from 385 to 470 MPa at 500 degrees C. Strengthening became more effective as the test temperature increased. It was noted that brittle fracture occurred at room temperature, which was not observed at elevated temperatures. Resistance to dynamic high-temperature bursting improved. The burst temperature increased from 760 to 830 degrees C at a heating rate of 5 degrees C/s and internal pressure of 8.3 MPa. The burst opening was also smaller than those in fresh Zircaloy-4 tubes. This method is expected to enhance the safety of Zr fuel cladding tubes owing to the improvement of their mechanical properties. (C) 2018 Korean Nuclear Society, Published by Elsevier Korea LLC.
引用
收藏
页码:218 / 222
页数:5
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