Abstract: As the candidate structural material for the fourth generation advanced reactor and the first wall for fusion reactor, the irradiation resistance of oxide dispersion strengthened (ODS) alloy is still a key problem restricting its application in fast reactor and fusion reactor. In this paper, 570 groups of data containing composition, sintering and heat treatment process, irradiation condition, test condition and yield strength were collected. The data above were cleaned and screened before model training. By using the deep neural network with back propagation, the relationship between Cr, Y₂O₃ and other key component and neutron irradiation hardening of ODS alloy was established, and the irradiation hardening prediction of ODS alloy was obtained. The results show that the irradiation hardening of ODS alloy decreases when the content of Cr is about 6% and the content of Y₂O₃ is about 0.2%. Besides, the addition of Ti is beneficial to reduce the irradiation hardening of ODS alloy, while the addition of Al will aggravate the irradiation hardening. Based on these, the composition design of ODS alloy with less irradiation hardening under certain irradiation condition can be obtained further.