Hızlandırıcı Sürücülü Sistemlerde MOX ve Toryum Dioksit Yakıtlarının Performans Analizi

Year 2025, Volume: 13 Issue: 3, 1289 - 1296, 31.07.2025

Büşra Durmaz , Alper Buğra Arslan , Hüseyin Yapıcı

https://doi.org/10.29130/dubited.1662715

Abstract

Hızlandırıcı sürücülü sistemler (HSS), yüksek enerjiye sahip parçacık demetlerini kullanarak tıbbi
radyoizotop üretimi, nükleer atık dönüşümü temiz enerji üretimi gibi alanlarda yenilikçi çözümler ortaya
koyan sistemlerdir. HSS’ler gelecekte sağlık ve enerji alanlarındaki problemlerin çözümlenmesinde
önemli bir rol oynayacaktır. Çalışmada, HSS’in yakıt bölgesine plütonyum dioksit (PuO2) ve toryum
dioksit (ThO2) yakıtları farklı oranlarda karıştırılarak konulmuştur. Buradaki PuO2 yakıtı termal
reaktörlerden atık olarak ortaya çıkan MOX yakıtı içerisinden alınmıştır. Sisteme konulan diğer yakıt
türü toryum ise, HSS’in hedef bölgesinden açığa çıkan nötronlarla reaksiyona girerek 233U izotopuna
dönüşmekte ve bu süreç de enerji üretimine katkıda bulunmaktadır. Böylelikle termal reaktörlerin çalışması sonucu açığa çıkan atıklar, Hızlandırıcı Sürücülü Sistemlerde (HSS) yeniden değerlendirilerek
hem çevresel zararın azaltılmasına hem de sistemin ek enerji üretimine katkı sağlamaktadır. HSS’in
verimli bir şekilde çalışmasında önemli bir parametre olan nötron çoğaltma faktörü 0.98 civarında
tutulmuştur. Nötronik analizlerin gerçekleştirilmesinde MCNPX 2.7 ve onunla entegre bir şekilde
çalışan CINDER 90 programlarından faydalanılmıştır.

Keywords

HSS , MOX , MCNPX 2.7 , Toryum dioksit

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

ADS , MOX , MCNPX 2.7 , Thorium dioxide

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