Performance Analysis of MOX and Thorium Dioxide Fuels in Accelerator-Driven Systems
Abstract
Accelerator-Driven Systems (ADS) utilize high-energy particle beams to provide innovative solutions
in fields such as medical radioisotope production, nuclear waste transmutation, and clean energy
generation. ADS is expected to play a significant role in solving future challenges in healthcare and
energy. In this study, plutonium dioxide (PuO2) and thorium dioxide (ThO2) fuels were mixed in
different ratios and placed in the fuel region of the ADS. The PuO₂ fuel used in this system was extracted
from MOX fuel, which is a byproduct of thermal reactors. The other fuel type, thorium, reacts with
neutrons released from the target region of the ADS, converting into uranium-233 (233U), which
contributes to energy production. Thus, waste generated by thermal reactors is reutilized in Accelerator-
Driven Systems (ADS), reducing environmental harm while also contributing to additional energy
production. The neutron multiplication factor, a crucial parameter for the efficient operation of ADS,
was maintained at approximately 0.98. Neutronic analyses were performed using the MCNPX 2.7 code
and its integrated CINDER 90 program.
Keywords
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