Verification of source term estimation method against measured data for spent fuel hardware characterization

The Republic of Korea has developed an advanced source term analysis tool, called ASOURCE, to support R&D action plans for the achievement of an advanced fuel cycle employing a pyroprocess in connection with a sodium-cooled fast reactor. ASOURCE has the following functions: (a) generation of inflow and outflow source terms of mixed spent fuel (SF) in each process for the design of the pyroprocess facility; (b) overall inventory estimation for Transuranics (TRUs) and long-lived nuclides in SFs stored at each or all reactor sites for the design of the SFR; and (c) grand source terms of a batch of SFs with different irradiation and cooling profiles for the practical design of a temporary or interim storage facility of SFs. ASOURCE is comprised of three analysis sequences, a Fuel Waste Characterization Sequence, Metal Waste Characterization Sequence, and Grand Source Term Characterization Sequence. In this study, the Metal Waste Characterization Sequence was verified by comparing the nuclide inventory estimated by ASOURCE with the measured nuclide inventory in an irradiated grid plate. It was found that the values calculated by ASOURCE agreed with the measured data within 35%, indicating that the developed program supplies viable source term data.

► The Republic of Korea has developed an advanced source term analysis tool, called ASOURCE, to support R&D action plans.
► It is comprised of three analysis sequences for fuel waste, metal waste, and grand source term characterizations.
► The sequence for metal waste characterization was verified by the measured nuclide inventory.
► The calculated values agreed with the measured data within 35%, indicating that ASOURCE supplies viable source term data.