Shengjie Wang , Jing Yao , Shuying Zhen , Yanli Wang , Ying Yu , Chunlei Zhao , Shilei Li , Yandong Wang
{"title":"喷丸强化对Inconel 690合金显微组织、残余应力和力学性能的影响","authors":"Shengjie Wang , Jing Yao , Shuying Zhen , Yanli Wang , Ying Yu , Chunlei Zhao , Shilei Li , Yandong Wang","doi":"10.1016/j.jnucmat.2025.156224","DOIUrl":null,"url":null,"abstract":"<div><div>Inconel 690 alloy is a key structural material for heat transfer tubes in pressurized water reactor nuclear power plants, where it endures harsh service conditions. Shot peening (SP) is a widely adopted surface treatment technique to enhance the durability and extend the service life of such components. This study systematically examines the effects of SP process parameters, including shot material, peening intensity, and peening coverage, on the microstructure, residual stress, and mechanical properties of Inconel 690 alloy. The results reveal that SP produces a pronounced gradient microstructure comprising a nanocrystalline surface layer, a plastically deformed sub-surface region, and a deep compressive residual stress field extending to about 240 μm. Moreover, SP induces a gradient compressive residual stress field in Inconel 690 alloy, with the magnitude and penetration depth strongly influenced by shot material, peening intensity, and coverage. The surface modifications significantly improve the mechanical performance: the yield strength increases by up to 62.4 % (from 311 MPa to 505 MPa for the SP-300 % sample), and surface hardness rises by approximately 68.5 % (from 2.990 GPa to 5.038 GPa), albeit with a slight reduction in ductility. Additionally, all SP-treated samples exhibit enhanced wear resistance, as evidenced by reduced specific wear rates due to surface hardening. This work delivers fundamental mechanism understanding of the effects of shot peening on microstructure and mechanical properties, and guides the systematic screening and optimization of SP parameters such as shot material, peening intensity, and coverage.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"618 ","pages":"Article 156224"},"PeriodicalIF":3.2000,"publicationDate":"2025-10-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Effect of shot peening on the microstructure, residual stress, and mechanical properties of Inconel 690 alloy\",\"authors\":\"Shengjie Wang , Jing Yao , Shuying Zhen , Yanli Wang , Ying Yu , Chunlei Zhao , Shilei Li , Yandong Wang\",\"doi\":\"10.1016/j.jnucmat.2025.156224\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Inconel 690 alloy is a key structural material for heat transfer tubes in pressurized water reactor nuclear power plants, where it endures harsh service conditions. Shot peening (SP) is a widely adopted surface treatment technique to enhance the durability and extend the service life of such components. This study systematically examines the effects of SP process parameters, including shot material, peening intensity, and peening coverage, on the microstructure, residual stress, and mechanical properties of Inconel 690 alloy. The results reveal that SP produces a pronounced gradient microstructure comprising a nanocrystalline surface layer, a plastically deformed sub-surface region, and a deep compressive residual stress field extending to about 240 μm. Moreover, SP induces a gradient compressive residual stress field in Inconel 690 alloy, with the magnitude and penetration depth strongly influenced by shot material, peening intensity, and coverage. The surface modifications significantly improve the mechanical performance: the yield strength increases by up to 62.4 % (from 311 MPa to 505 MPa for the SP-300 % sample), and surface hardness rises by approximately 68.5 % (from 2.990 GPa to 5.038 GPa), albeit with a slight reduction in ductility. Additionally, all SP-treated samples exhibit enhanced wear resistance, as evidenced by reduced specific wear rates due to surface hardening. This work delivers fundamental mechanism understanding of the effects of shot peening on microstructure and mechanical properties, and guides the systematic screening and optimization of SP parameters such as shot material, peening intensity, and coverage.</div></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"618 \",\"pages\":\"Article 156224\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-10-14\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Nuclear Materials\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S002231152500618X\",\"RegionNum\":2,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q3\",\"JCRName\":\"MATERIALS SCIENCE, MULTIDISCIPLINARY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S002231152500618X","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
Effect of shot peening on the microstructure, residual stress, and mechanical properties of Inconel 690 alloy
Inconel 690 alloy is a key structural material for heat transfer tubes in pressurized water reactor nuclear power plants, where it endures harsh service conditions. Shot peening (SP) is a widely adopted surface treatment technique to enhance the durability and extend the service life of such components. This study systematically examines the effects of SP process parameters, including shot material, peening intensity, and peening coverage, on the microstructure, residual stress, and mechanical properties of Inconel 690 alloy. The results reveal that SP produces a pronounced gradient microstructure comprising a nanocrystalline surface layer, a plastically deformed sub-surface region, and a deep compressive residual stress field extending to about 240 μm. Moreover, SP induces a gradient compressive residual stress field in Inconel 690 alloy, with the magnitude and penetration depth strongly influenced by shot material, peening intensity, and coverage. The surface modifications significantly improve the mechanical performance: the yield strength increases by up to 62.4 % (from 311 MPa to 505 MPa for the SP-300 % sample), and surface hardness rises by approximately 68.5 % (from 2.990 GPa to 5.038 GPa), albeit with a slight reduction in ductility. Additionally, all SP-treated samples exhibit enhanced wear resistance, as evidenced by reduced specific wear rates due to surface hardening. This work delivers fundamental mechanism understanding of the effects of shot peening on microstructure and mechanical properties, and guides the systematic screening and optimization of SP parameters such as shot material, peening intensity, and coverage.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.