{"title":"Effect of brazing parameters on the microstructure and mechanical properties of SiC ceramic joint with Zr-Cu-Nb filler metal","authors":"Bofang Zhou , Zixuan Leng , Hongxia Zhang , Zhaojie Zhang , Wuman Wang","doi":"10.1016/j.net.2025.103547","DOIUrl":null,"url":null,"abstract":"<div><div>The excellent properties of SiC ceramic make them possible to replace zirconium alloy and become the 4th generation of nuclear power plant cladding material. In this study, the microstructure and mechanical properties of SiC ceramic joint with Zr-Cu-Nb powder filler metal under different brazing temperature and holding time were investigated. The results show that Zr-Cu-Nb filler metal can effectively braze SiC ceramic at different brazing temperature (950<span><math><mo>∼</mo></math></span>1150 °C) with the holding time of 20 min. The primary phases in the interface reaction layer are mainly ZrC and Zr<sub>2</sub>Si. The shear strength of the joint first increases and then decreases with the brazing temperature, reaching a maximum of 135 MPa at 1050 °C under the holding time of 20 min. The joint primarily fractures at the reaction layer, exhibiting brittle fracture behavior. The thickness of the interface reaction layer increases with the holding time(5<span><math><mo>∼</mo></math></span>60min) under the brazing temperature of 1050 °C. The shear strength of the joint reaches its maximum of 135 MPa at 20 min under the brazing temperature of 1050 °C, with the thickness of the reaction layer being 1.2 <span><math><mi>μ</mi></math></span>m. The joint primarily fractures at the reaction layer, exhibiting brittle fracture behavior.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103547"},"PeriodicalIF":2.6000,"publicationDate":"2025-02-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S1738573325001159","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The excellent properties of SiC ceramic make them possible to replace zirconium alloy and become the 4th generation of nuclear power plant cladding material. In this study, the microstructure and mechanical properties of SiC ceramic joint with Zr-Cu-Nb powder filler metal under different brazing temperature and holding time were investigated. The results show that Zr-Cu-Nb filler metal can effectively braze SiC ceramic at different brazing temperature (9501150 °C) with the holding time of 20 min. The primary phases in the interface reaction layer are mainly ZrC and Zr2Si. The shear strength of the joint first increases and then decreases with the brazing temperature, reaching a maximum of 135 MPa at 1050 °C under the holding time of 20 min. The joint primarily fractures at the reaction layer, exhibiting brittle fracture behavior. The thickness of the interface reaction layer increases with the holding time(560min) under the brazing temperature of 1050 °C. The shear strength of the joint reaches its maximum of 135 MPa at 20 min under the brazing temperature of 1050 °C, with the thickness of the reaction layer being 1.2 m. The joint primarily fractures at the reaction layer, exhibiting brittle fracture behavior.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development