Published June 2022 | Version v1
Journal article

Composition optimization of radiation resistance ODS alloy with high strength and ductility for advanced reactor based on machine learning

  • 1. Reactor Engineering Technology Research Institute, China Institute of Atomic Energy, Beijing (China)

Description

Oxide dispersion strengthened (ODS) alloy is a candidate material for cladding in the fast reactor and the first wall in fusion reactor. Its radiation resistance is still a key problem restricting its application in the field of fast reactor and fusion reactor. By collecting, cleaning and screening the data which includes the composition, process, irradiation conditions, test conditions and yield strength of ODS alloy, the correlation between key components and irradiation hardening of ODS alloy were established by use of deep neural network, and the irradiation hardening prediction of ODS alloy was obtained. The results show that the irradiation hardening decreases significantly when the amount of Y2O3 is about 0.2%. In addition, it is found that when the addition of Y2O3 is greater than 0.3 wt%, the addition of Ti and Al has little effect on the irradiation hardening, while when the addition of Y2O3 is less than 0.2 wt%, the addition of a certain amount of Ti or Al will effectively inhibit the irradiation hardening of ODS alloy. According to the above results, combined with the high strength and ductility ODS alloy design obtained in the previous work, the composition optimization of ODS alloy with both strengthening and toughening and irradiation hardening resistance is further obtained. (author)

Availability note (English)

Available from DOI: https://doi.org/10.1080/00223131.2021.2004952

Additional details

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo) (Online)
Journal Volume
59
Journal Issue
6
Journal Page Range
p. 725-734
ISSN
1881-1248

Optional Information

Notes
37 refs., 7 figs., 2 tabs.