Irradiation damage in construction materials for fusion reactors

Horizontal and vertical section lines are shown of the UWMAK-I concept, an experimental fusion reactor of the University of Wisconsin. The reactor is of the Tokamak type. Flux energy and distribution features are outlined. Results are given for irradiation damage and swelling in SS 316 steel as functions of irradiation dose and temperature. Damage studies in neutron fluxes by the (n, α) reaction in SS 304 have also been made. Surface effects are also studied, with special reference to erosion speed. (G.C.)