Multiscale microstructure-based constitutive modeling of high-temperature creep rupture in post-irradiated ODS steels
Oxide dispersion strengthened (ODS) steel exhibits the great potential as structural materials in nuclear energy production, owing to the complex interface between the oxide particles and the matrix to enhance the resistance of radiation damage. However, the impact of irradiation-induced defects on...
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Elsevier
2025-05-01
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| Series: | Journal of Materials Research and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S2238785425012074 |
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| author | Xiaobao Fu Zhenyu Zhao Zeyuan Yan Yuntao Zhong Dengke Chen Ruiqian Zhang Bin Liu Qihong Fang Jia Li |
| author_facet | Xiaobao Fu Zhenyu Zhao Zeyuan Yan Yuntao Zhong Dengke Chen Ruiqian Zhang Bin Liu Qihong Fang Jia Li |
| author_sort | Xiaobao Fu |
| collection | DOAJ |
| description | Oxide dispersion strengthened (ODS) steel exhibits the great potential as structural materials in nuclear energy production, owing to the complex interface between the oxide particles and the matrix to enhance the resistance of radiation damage. However, the impact of irradiation-induced defects on the thermal creep rate and resistance of ODS steel currently remains inadequately understood. The point defect concentration with the increasing time is predicted, and the coarsening of oxide particles is quantitatively evaluated during the creep using the Ostwald ripening theory. Considering the irradiation-induced microstructure, a modified thermal creep rate model is proposed, and the thermal creep rate and creep strain of irradiated ODS steel are predicted at different temperatures. The results show that the thermal creep rate reaches 3 × 10−5 s−1 at the temperature of 500 °C and stress of 200 MPa, while the thermal creep strain does not exceed 3 % at the temperature of 800 °C. The average size and number density of the irradiated ODS steel are 8.34 nm and 2.72 × 1018 m−3. Meanwhile, the effect of the activation energy on the thermal creep life is predicted at different temperatures. The thermal creep life is maintained in the higher temperature range, even exceeding 10,000 h at 600 °C for irradiated ODS steels. High temperature causes the increased dislocation activity, and the coarsened oxide particles effectively hinder dislocation motion, thereby maintaining structural stability. This work aims to shed light on the influence of post-irradiation microstructure on the thermal creep performance of irradiated ODS steels, ultimately leading to the improved prediction of creep life. |
| format | Article |
| id | doaj-art-7a5aaec5925b4fda98c2bda731d78743 |
| institution | Kabale University |
| issn | 2238-7854 |
| language | English |
| publishDate | 2025-05-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Journal of Materials Research and Technology |
| spelling | doaj-art-7a5aaec5925b4fda98c2bda731d787432025-08-20T03:49:46ZengElsevierJournal of Materials Research and Technology2238-78542025-05-01368037804710.1016/j.jmrt.2025.05.052Multiscale microstructure-based constitutive modeling of high-temperature creep rupture in post-irradiated ODS steelsXiaobao Fu0Zhenyu Zhao1Zeyuan Yan2Yuntao Zhong3Dengke Chen4Ruiqian Zhang5Bin Liu6Qihong Fang7Jia Li8State Key Laboratory of Advanced Design and Manufacturing Technology for Vehicle, College of Mechanical and Vehicle Engineering, Hunan University, Changsha, 410082, PR ChinaState Key Laboratory of Powder Metallurgy, Central South University, Changsha, 410083, PR ChinaState Key Laboratory of Advanced Design and Manufacturing Technology for Vehicle, College of Mechanical and Vehicle Engineering, Hunan University, Changsha, 410082, PR ChinaScience and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, 610213, PR ChinaDepartment of Engineering Mechanics, School of Ocean and Civil Engineering, Shanghai Jiao Tong University, Shanghai, 200240, PR ChinaScience and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, 610213, PR China; Corresponding author.State Key Laboratory of Powder Metallurgy, Central South University, Changsha, 410083, PR China; Corresponding author.State Key Laboratory of Advanced Design and Manufacturing Technology for Vehicle, College of Mechanical and Vehicle Engineering, Hunan University, Changsha, 410082, PR ChinaState Key Laboratory of Advanced Design and Manufacturing Technology for Vehicle, College of Mechanical and Vehicle Engineering, Hunan University, Changsha, 410082, PR China; Corresponding author.Oxide dispersion strengthened (ODS) steel exhibits the great potential as structural materials in nuclear energy production, owing to the complex interface between the oxide particles and the matrix to enhance the resistance of radiation damage. However, the impact of irradiation-induced defects on the thermal creep rate and resistance of ODS steel currently remains inadequately understood. The point defect concentration with the increasing time is predicted, and the coarsening of oxide particles is quantitatively evaluated during the creep using the Ostwald ripening theory. Considering the irradiation-induced microstructure, a modified thermal creep rate model is proposed, and the thermal creep rate and creep strain of irradiated ODS steel are predicted at different temperatures. The results show that the thermal creep rate reaches 3 × 10−5 s−1 at the temperature of 500 °C and stress of 200 MPa, while the thermal creep strain does not exceed 3 % at the temperature of 800 °C. The average size and number density of the irradiated ODS steel are 8.34 nm and 2.72 × 1018 m−3. Meanwhile, the effect of the activation energy on the thermal creep life is predicted at different temperatures. The thermal creep life is maintained in the higher temperature range, even exceeding 10,000 h at 600 °C for irradiated ODS steels. High temperature causes the increased dislocation activity, and the coarsened oxide particles effectively hinder dislocation motion, thereby maintaining structural stability. This work aims to shed light on the influence of post-irradiation microstructure on the thermal creep performance of irradiated ODS steels, ultimately leading to the improved prediction of creep life.http://www.sciencedirect.com/science/article/pii/S2238785425012074IrradiationOxide dispersion strengtheningPoint defectThermal creep rate |
| spellingShingle | Xiaobao Fu Zhenyu Zhao Zeyuan Yan Yuntao Zhong Dengke Chen Ruiqian Zhang Bin Liu Qihong Fang Jia Li Multiscale microstructure-based constitutive modeling of high-temperature creep rupture in post-irradiated ODS steels Journal of Materials Research and Technology Irradiation Oxide dispersion strengthening Point defect Thermal creep rate |
| title | Multiscale microstructure-based constitutive modeling of high-temperature creep rupture in post-irradiated ODS steels |
| title_full | Multiscale microstructure-based constitutive modeling of high-temperature creep rupture in post-irradiated ODS steels |
| title_fullStr | Multiscale microstructure-based constitutive modeling of high-temperature creep rupture in post-irradiated ODS steels |
| title_full_unstemmed | Multiscale microstructure-based constitutive modeling of high-temperature creep rupture in post-irradiated ODS steels |
| title_short | Multiscale microstructure-based constitutive modeling of high-temperature creep rupture in post-irradiated ODS steels |
| title_sort | multiscale microstructure based constitutive modeling of high temperature creep rupture in post irradiated ods steels |
| topic | Irradiation Oxide dispersion strengthening Point defect Thermal creep rate |
| url | http://www.sciencedirect.com/science/article/pii/S2238785425012074 |
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