Neutronic evaluation of candu-6 core using reprocessed fuels
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Universidade Federal de Minas Gerais
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The spent fuel from a PWR still contains some amount of fissile materials depending on their initial enrichment
and the burnup. Thus, spent fuel from PWRs containing about 1.5% of fissile material could be used as fuel for
CANDU reactors after some fission products are removed from it. Thus, an important proposal is the DUPIC
cycle, where spent fuels from a PWR are packaged into a CANDU fuel bundle using mechanical reprocessing but
without the need of chemical reprocessing. When it is refueled with reprocessed fuel, the reactivity of the system
increases, and this behavior may affect the safety parameters of the reactor. Therefore, this work studies the
neutronic parameters of two reprocessing fuel techniques: AIROX and OREOX, which are evaluated for two
different cores configuration. The first one considers heavy water as a moderator and coolant. The second one
considers heavy water and light water as moderator and coolant, respectively. These studies evaluate the core
behavior based on the different number of reprocessed fuels channels and compare them with the reference core.
To perform the simulation, MCNPX was used to calculate the effective multiplication factor, void reactivity
coefficient, and neutron flux, which were evaluated at steady state condition for the different cases. The results
show that the presence of parasitic absorbers in the reprocessed fuels hardens the neutron spectrum. This
behavior provokes an increase in the core reactivity, and in the void reactivity coefficient. Among these
parameters, the use of light water reduces the core reactivity but does not improve the void reactivity coefficient.
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CANDU reactor, DUPIC cycle, AIROX, OREOX, MCNPX 2.6.0
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https://www.bjrs.org.br/revista/index.php/REVISTA/article/view/1219