[en] Ferritic steels have been selected as candidate materials for first-wall applications in fusion reactors, because of their high resistance to swelling and low thermal expansion coefficient. To characterize the fracture behavior of these materials influenced by both displacement damage and transmutation produced helium at levels relevant to fusion reactor irradiation conditions, the fracture toughness of HT9 and 9Cr-1Mo irradiated to 10--20 dpa at 50/degree/C was evaluated using electric potential single specimen techniques. Circular compact tension specimens were tested at temperatures ranging from room temperature to 450/degree/C. The single specimen method was employed to minimize the number of specimens required to save irradiation space and to meet requirements for testing samples with a prototypic component thickness. Specimens of HT9 doped with 1 and 2% nickel to increase helium production during High Flux Isotope Reactor (HFIR) irradiation were also tested