The use of nuclear reactors with a fast neutron spectrum has emerged as a promising path towards achieving nuclear disarmament, due to their capability to burn plutonium and other minor actinides. The Collaboration Project between Alva Myrdal Centre and SUNRISE centre explores the feasibility and efficiency of plutonium disposal by using a lead-cooled fast reactor (LFR). The plutonium disposal efficiency, of the 80 MWth conceptual LFR design developed by the SUNRISE centre is evaluated with both mixed oxide and mixed nitride fuel. To evaluate the viability of plutonium disposal with the different fuel configurations numerous neutron transport calculations need to be performed, and the use of Monte Carlo neutron transport code Serpent 2 is proposed to perform them. The use of codes based on the Monte Carlo method requires a significant amount of computational resources to yield accurate and reliable results, for this reason, the computational resources provided by NAISS/PDC will enable multiple and highly parallelized calculations, leading to exploring detailed the feasibility of plutonium disposal in the LFR.