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Fuel breeding and waste burnup capabilities of an accelerator‐driven system using thorium and reprocessed fuels
Author(s) -
Barros Graiciany,
Campagnole dos Santos Andre A.,
Vasconcelos Vitor,
Campolina Daniel,
Pereira Claubia
Publication year - 2020
Publication title -
international journal of energy research
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.808
H-Index - 95
eISSN - 1099-114X
pISSN - 0363-907X
DOI - 10.1002/er.5886
Subject(s) - burnup , thorium fuel cycle , thorium , uranium , mox fuel , spent nuclear fuel , nuclear engineering , actinide , radiochemistry , waste management , natural uranium , nuclear fuel , plutonium 240 , rod , enriched uranium , radioactive waste , environmental science , materials science , nuclear chemistry , chemistry , plutonium 239 , neutron , nuclear physics , engineering , metallurgy , physics , fission , medicine , alternative medicine , pathology
Summary Fuel breeding and waste actinide burnup capabilities of a lead‐cooled accelerator‐driven system were evaluated using thorium and reprocessed fuels. The subcritical core simulated was filled with a hexagonal lattice formed by 232 ThO 2 rods and reprocessed fuel rods. Four types of reprocessed fuel were studied: Group ActiNide EXtraction (GANEX) fuel spiked with 51% of thorium, GANEX fuel spiked with 51% of depleted uranium, Uranium Extraction Plus (UREX + ) fuel spiked with 51% of thorium and UREX + fuel spiked with 51% of depleted uranium. The results indicated that the use of thorium and reprocessed fuels allows thorium regeneration and reduction of the inventory of high radiotoxicity isotopes. The Monte Carlo code SERPENT 2.1.31 was used for the simulations.