Currently, the study of fusion reactor first walls and structural materials is mainly being focused on austenitic and ferritic steels in China. A hydrogen embrittlement resistant austenitic steel, HR-1, and a ferritic steel, CHT-9, have been developed in China. To evaluate their prospects of application to fusion reactors, the electron irradiation effect on them has been studies by means of a high-voltage electron microscope (HVEM). The electron irradiation doses reached 19.2 dpa at temperatures of 773 and 673 K, and the experimental results are presented by microphotographs and curves. At maximum doses in this study the void number density, average void diameter, and swelling are 2.0E + 20/m3, 70 nm, and 4%, respectively. For comparison, the microphotographs of irradiated CHT-9 specimens are also given.