{"title":"Cyclic behaviors of diffusion welded alloy 800H","authors":"Jong-Bae Hwang , Eung-Seon Kim","doi":"10.1016/j.net.2025.103536","DOIUrl":null,"url":null,"abstract":"<div><div>Diffusion welding creates monolithic joints with complex interiors, such as in the printed circuit heat exchanger (PCHE) for high-temperature reactors. PCHEs are mainly subjected to low cycle fatigue, which is caused by thermal contraction and expansion during the start-up/shutdown. To utilize PCHEs in high-temperature reactors, it is essential to understand the cyclic behaviors of the diffusion weldment (DFW). In this study fatigue tests were conducted on Alloy 800H in its as-received (AR) state with the diffusion weldment at 650 °C and 760 °C and a total strain range of 0.5–1.2 %. The heat absorbed during the diffusion welding process softened the DFW, allowing it to accommodate large plastic strains. Fatigue tests revealed that the fatigue life of the DFW was longer than that of the AR where the plastic strain dominates the fatigue life. However, the fatigue life of the DFW was shorter than that of the AR where the materials resisted the cyclic behavior based on their strengths. The location of crack initiation was outside the diffusion welding interface, indicating that the cyclic behaviors of the diffusion weldment depend on the thermal history of the manufacturing process.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103536"},"PeriodicalIF":2.6000,"publicationDate":"2025-02-16","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/S1738573325001044","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
Diffusion welding creates monolithic joints with complex interiors, such as in the printed circuit heat exchanger (PCHE) for high-temperature reactors. PCHEs are mainly subjected to low cycle fatigue, which is caused by thermal contraction and expansion during the start-up/shutdown. To utilize PCHEs in high-temperature reactors, it is essential to understand the cyclic behaviors of the diffusion weldment (DFW). In this study fatigue tests were conducted on Alloy 800H in its as-received (AR) state with the diffusion weldment at 650 °C and 760 °C and a total strain range of 0.5–1.2 %. The heat absorbed during the diffusion welding process softened the DFW, allowing it to accommodate large plastic strains. Fatigue tests revealed that the fatigue life of the DFW was longer than that of the AR where the plastic strain dominates the fatigue life. However, the fatigue life of the DFW was shorter than that of the AR where the materials resisted the cyclic behavior based on their strengths. The location of crack initiation was outside the diffusion welding interface, indicating that the cyclic behaviors of the diffusion weldment depend on the thermal history of the manufacturing process.
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