Neutronic and nonproliferation characteristics of (PuO2–UO2) and (PuO2–ThO2) as fast reactor fuels

摘要: Abstract Computational core physics analysis carried out for a typical fast breeder reactor (FBR) design is presented through two case studies; one using only (PuO 2 –UO ) MOX fuel and another that replaces ∼41% of with –ThO while conserving the total Pu content. The basic computational framework employed uses MONTEBURNS2 PERL script to couple neutronic code, MCNP5 depletion/burn-up ORIGEN2.2. parameters computed compared are: net neutron multiplication factor ( k eff ); regionally averaged spectrum; flux; thermal power distribution; breeding ratio; burn-up; fissile material build-up/depletion- 232 U build-up; temperature dependent Doppler Effect, coolant sodium expansion coefficient, nonproliferation characteristics such as dose rates, spontaneous fission gamma emissions. analyses studies indicate characteristics, except , are marginally different in their magnitudes between cases, if not equal. first study shows diversion either 8 radial blanket sub-assemblies (weapon grade Pu) or 1 spent sub-assembly (reactor discharged from an equilibrium sufficient derive significant quantity (SQ). second considerable improvement proliferation resistance can be achieved peripheral loading pins all reactor, which should aid nuclear safeguards. comparison transuranic (TRU) generation both cases showed about 60% reduction neptunium production has been new proposed partially ThO –PuO loaded FBR design, whereas other higher TRUs like americium, curium, etc. did show reduction.