Abstract: Additive manufacturing of 316L stainless steel has broad application prospects in the field of nuclear energy due to its excellent processing accuracy, surface quality, comprehensive mechanical properties, and corrosion resistance. However, when nuclear structural materials are used in irradiation environments, the defects generated by irradiation can lead to a decrease in material performance. In order to ensure the stability of the performance of AM 316L stainless steel under irradiation environment, the study of its irradiation damage effect has gradually become a hot topic of attention both domestically and internationally. Therefore, the research progress on the structure, properties, and radiation resistance of AM 316L stainless steel commonly used in the field of nuclear energy is reviewed, and some suggestions for future research directions are proposed in the article.