A.J. Cackett , H. Wilcox , A. Kite , J. Ferriday , N. Riddle , P.D. Styman
{"title":"低合金钢辐照后退火研究:确定基体损伤和聚类对硬化的贡献","authors":"A.J. Cackett , H. Wilcox , A. Kite , J. Ferriday , N. Riddle , P.D. Styman","doi":"10.1016/j.jnucmat.2025.156144","DOIUrl":null,"url":null,"abstract":"<div><div>In this work, post-irradiation annealing (PIA) at temperatures up to 425 °C was carried out on two low-Cu steels with varying Mn content that were irradiated at high flux to doses up to ∼0.1 dpa. Atom probe tomography (APT) was used to characterise the number, size, and composition of clusters in the as-irradiated material and select PIA samples, and the results compared alongside irradiation-induced change in hardness. For both steels it was found that as annealing temperature increased there was dissolution of Mn and Si from the clusters into the surrounding matrix. The number density and volume fraction of clusters were found to decrease with increasing annealing temperature. As expected from particle hardening models, the change in hardness due to irradiation was proportional to the square root of cluster volume fraction normalised by cluster size for the PIA material. The as-irradiated material, however, deviated from this trend. It is proposed that the observed increase above the expected hardening for the as-irradiated material is attributed with unstable matrix damage, which cannot be directly characterised by APT.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156144"},"PeriodicalIF":3.2000,"publicationDate":"2025-09-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Post-irradiation annealing study on low-alloy steels: Determining the contributions of matrix damage and clustering to hardening\",\"authors\":\"A.J. Cackett , H. Wilcox , A. Kite , J. Ferriday , N. Riddle , P.D. Styman\",\"doi\":\"10.1016/j.jnucmat.2025.156144\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In this work, post-irradiation annealing (PIA) at temperatures up to 425 °C was carried out on two low-Cu steels with varying Mn content that were irradiated at high flux to doses up to ∼0.1 dpa. Atom probe tomography (APT) was used to characterise the number, size, and composition of clusters in the as-irradiated material and select PIA samples, and the results compared alongside irradiation-induced change in hardness. For both steels it was found that as annealing temperature increased there was dissolution of Mn and Si from the clusters into the surrounding matrix. The number density and volume fraction of clusters were found to decrease with increasing annealing temperature. As expected from particle hardening models, the change in hardness due to irradiation was proportional to the square root of cluster volume fraction normalised by cluster size for the PIA material. The as-irradiated material, however, deviated from this trend. It is proposed that the observed increase above the expected hardening for the as-irradiated material is attributed with unstable matrix damage, which cannot be directly characterised by APT.</div></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"617 \",\"pages\":\"Article 156144\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-09-02\",\"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/S0022311525005380\",\"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/S0022311525005380","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}
Post-irradiation annealing study on low-alloy steels: Determining the contributions of matrix damage and clustering to hardening
In this work, post-irradiation annealing (PIA) at temperatures up to 425 °C was carried out on two low-Cu steels with varying Mn content that were irradiated at high flux to doses up to ∼0.1 dpa. Atom probe tomography (APT) was used to characterise the number, size, and composition of clusters in the as-irradiated material and select PIA samples, and the results compared alongside irradiation-induced change in hardness. For both steels it was found that as annealing temperature increased there was dissolution of Mn and Si from the clusters into the surrounding matrix. The number density and volume fraction of clusters were found to decrease with increasing annealing temperature. As expected from particle hardening models, the change in hardness due to irradiation was proportional to the square root of cluster volume fraction normalised by cluster size for the PIA material. The as-irradiated material, however, deviated from this trend. It is proposed that the observed increase above the expected hardening for the as-irradiated material is attributed with unstable matrix damage, which cannot be directly characterised by APT.
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.