NEUTRON DAMAGE AND ACTIVATION OF THE 1ST WALL OF INERTIAL CONFINEMENTFUSION-REACTORS - RECYCLING AND WASTE-DISPOSAL

Even though general conclusions cannot be derived for all the protecti on schemes in inertial confinement fusion (ICF) reactors, the feasibil ity of the ferritic alloy HT-9 as the main component of the first stru ctural wall (FSW) in ICF facilities using thin-film Li17Pb83 liquid pr otection, flowing through porous tubes (INPORT), can be demonstrated a s a solution in terms of radiation damage. Swelling and shift in the d uctile-brittle transition temperature (DBTT) can be analyzed using the results of experimental fast-fission reactors, which are demonstrated to be good experimental tools in that ICF range. The good performance of HT-9 is remarkable. The generation of new solid transmutants and t he depletion of initial constituents need also be considered. Further, a reduced-activation HT-9 (niobium-free) has been studied using recyc ling and shallow land burial (SLB) criteria. The recycling using that HT-9 is shown to be not feasible, as is SLB waste disposal. The unexpe cted critical role of some short-lived isotopes is remarkable, and mor e research on their nuclear data must be performed.