|About this Abstract
||2022 TMS Annual Meeting & Exhibition
||Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
||Impact Fretting Wear Behavior of Cr-alloy Coating Layer for Accident-tolerant Fuel cladding
||Youngho Lee, Dong-Jun Park, Yang-Il Jung, Sung-Chan Yoo, Hyun_Gil Kim
|On-Site Speaker (Planned)
Cr-alloy coated fuel cladding was proposed to improve resistance to corrosion in high temperature steam, which was coated with various coating methods on the conventional Zr-based fuel cladding. When a certain gap is opened between the fuel cladding and the spacer grid due to spring relaxation and irradiation during the normal operations, fretting wear mode can be changed from positive contact force to impacting wear. In this study, impact fretting wear characteristics of Cr-alloy coating layer were evaluated in various impact force, velocity and displacement in room temperature water. Fractured layer and trapped wear debris in the grooves were predominantly observed in the Zr-based cladding, whereas flat-like deformed layer and no crack formation was observed in the Cr-alloy coating layer. It is concluded that the Cr-alloy coating layer showed improved fretting wear resistance without any significant degradation under small impacting force below 3 N.
||Nuclear Materials, Surface Modification and Coatings, Mechanical Properties