Abstract
In the pressurized water reactor nuclear power plant, 316L SS chips were captured by the support grid and continued to affect the Zr-4 cladding tube, causing the fuel rods to wear and perforate. In this work, a 60° acute angle cone of 316L SS was used to simulate the cyclic impact of debris on a Zr-4 alloy tube with different initial impact velocities and impact angles. Results showed that increasing the initial impact velocity will generate a wear debris accumulation layer with a wear-reducing effect, but also promote the extension and expansion of fatigue cracks, resulting in the delamination of Zr-4 alloy tubes. The inclination of the impact angle increases the energy loss. The energy loss rate of the 45° impact is as high as 69.68%, of which 78% is generated by the impact-sliding stage. The normal force is mainly responsible for the wear removal and plastic deformation of Zr-4 alloy tubes. Tangential forces cause severe cutting in Zr-4 alloys and pushes the resulting wear debris away from the contact surfaces.
Funder
Sichuan Science and Technology Planning Project
Subject
General Materials Science
Reference33 articles.
1. Effects of ion irradiation on microstructure and properties of zirconium alloys—A review
2. A review of fretting study on nuclear power equipment
3. Diffusing Hydrogen Effect on the Oxide Film on 316l SS in High Temperature Water;Ma;Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors,2019
4. Effects of temperature on lectrochemical corrosion of domestic nuclear-grade 316L Stainless Steel in Zn-injected aqueous environment;Liu;Acta Metall. Sin.,2014
5. Wear behavior of zirconium-4 alloy after different irradiation damage level