{"title":"Effect of microstructural features on tensile properties of β-Quenched Zr-2.5 %Nb alloy","authors":"Aishwarya Upadhye , Arnomitra Chatterjee , A.K. Bind , Saurav Sunil , Apu Sarkar , R.N. Singh","doi":"10.1016/j.jnucmat.2025.155958","DOIUrl":null,"url":null,"abstract":"<div><div>Zr-2.5 %Nb alloy in the cold-worked and stress-relieved (CWSR) condition is used as pressure tube (PT) material in Pressurized Heavy Water Reactors (PHWRs) with a design life of 30 years. To enhance in-reactor performance, an alternative fabrication route involving heat treatment is being explored for Indian PHWRs<strong>.</strong> For the development of heat-treated pressure tubes, it is essential to optimize process parameters to achieve the desired microstructure and texture. Among microstructural factors, prior β-grain size is crucial in determining the mechanical properties of the material. In this study, Zr-2.5 %Nb alloy specimens were exposed to varying temperatures within the β-phase region for different soaking times. Rapid heating and quenching techniques were employed to ensure the formation of a random texture. The prior β-grain size was assessed using optical microscopy, while the martensitic lath structure was characterized through electron backscatter diffraction (EBSD). The tensile properties of the heat-treated specimens were evaluated at room temperature. The study tracked the evolution of prior β-grain size over time to identify different stages of grain growth. This work investigates the influence of prior β-grain size, martensitic lath structure, and dislocation density on the tensile properties of the β-quenched Zr-2.5 %Nb alloy.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"615 ","pages":"Article 155958"},"PeriodicalIF":3.2000,"publicationDate":"2025-06-03","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/S0022311525003526","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}
引用次数: 0
Abstract
Zr-2.5 %Nb alloy in the cold-worked and stress-relieved (CWSR) condition is used as pressure tube (PT) material in Pressurized Heavy Water Reactors (PHWRs) with a design life of 30 years. To enhance in-reactor performance, an alternative fabrication route involving heat treatment is being explored for Indian PHWRs. For the development of heat-treated pressure tubes, it is essential to optimize process parameters to achieve the desired microstructure and texture. Among microstructural factors, prior β-grain size is crucial in determining the mechanical properties of the material. In this study, Zr-2.5 %Nb alloy specimens were exposed to varying temperatures within the β-phase region for different soaking times. Rapid heating and quenching techniques were employed to ensure the formation of a random texture. The prior β-grain size was assessed using optical microscopy, while the martensitic lath structure was characterized through electron backscatter diffraction (EBSD). The tensile properties of the heat-treated specimens were evaluated at room temperature. The study tracked the evolution of prior β-grain size over time to identify different stages of grain growth. This work investigates the influence of prior β-grain size, martensitic lath structure, and dislocation density on the tensile properties of the β-quenched Zr-2.5 %Nb alloy.
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.