Hızlandırıcı Sürücülü Sistemlerde MOX ve Toryum Dioksit Yakıtlarının Performans Analizi

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

References

1. [1] G. P. Barros, C. Pereira, M. A. F. Veloso and A. L. Costa, “Thorium and reprocessed fuel utilization in an accelerator-driven system,” Annals of Nuclear Energy, vol. 80, pp. 14–20, 2015.
2. [2] G. P. Barros, C. Pereira, M. A. F. Veloso and A. L. Costa, “Study of an ADS loaded with thorium and reprocessed fuel,” Science and Technology of Nuclear Installations, vol. 2012, 2012, Art. no. 934105.
3. [3] T. M. Vu and T. Kitada, “Transmutation strategy using thorium-reprocessed fuel ADS for future reactors in Vietnam,” Science and Technology of Nuclear Installations, vol. 2013, 2013, Art. no. 674638.
4. [4] A. Abánades and A. Pérez-Navarro, “Engineering design studies for the transmutation of nuclear wastes with a gas-cooled pebble-bed ADS,” Nuclear Engineering and Design, vol. 237, no. 3, pp. 325–333, 2007.
5. [5] K. Tsujimoto, T. Sasa, K. Nishihara, H. Oigawa and H. Takano, “Neutronics design for leadbismuth cooled accelerator-driven system for transmutation of minor actinide,” Journal of Nuclear Science and Technology, vol. 41, no. 1, pp. 21–36, 2004.
6. [6] H. Yapıcı, G. Genç and N. Demir, “Neutronic limits in infinite target mediums driven by high energetic protons,” Annals of Nuclear Energy, vol. 34, no. 5, pp. 374–384, 2007.
7. [7] G. Bakır, B. S. Selçuklu, G. Genç and H. Yapıcı, “Neutronic analysis of LBE–uranium spallation target accelerator driven system loaded with uranium dioxide in TRISO particles,” Acta Physica Polonica A, vol. 129, no. 1, pp. 30–32, 2016.
8. [8] C. H. Cho, T. Y. Song and N. I. Tak, “Numerical design of a 20 MW lead–bismuth spallation target for an accelerator-driven system,” Nuclear Engineering and Design, vol. 229, no. 2–3, pp. 317– 327, 2004.

9. [9] S. Şahin, K. Yıldız, H. M. Şahin and A. Acır, “Investigation of CANDU reactors as a thorium burner,” Energy Conversion and Management, vol. 47, no. 13–14, pp. 1661–1675, 2006.
10. [10] A. M. Attom, J. Wang, J. Huang, C. Yan and M. Ding, “Comparison of homogeneous and heterogeneous thorium fuel blocks with four drivers in advanced high temperature reactors,” International Journal of Energy Research, vol. 44, no. 7, pp. 5713–5729, 2020.
11. [11] C. García et al., “Evaluation of uranium–thorium and plutonium–thorium fuel cycles in a very high temperature hybrid system,” Progress in Nuclear Energy, vol. 66, pp. 61–72, 2013.
12. [12] H. Ding, G. Quan, L. Hao, J. Song and W. Yican, “Verification and application of SuperMC3.3 to lead–bismuth-cooled fast reactor,” Nuclear Technology and Radiation Protection, vol. 34, no. 2, pp. 122–128, 2019.
13. [13] A. B. Arslan, I. Yılmaz, G. Bakır and H. Yapıcı, “Transmutations of long-lived and medium-lived fission products extracted from CANDU and PWR spent fuels in an accelerator-driven system,” Science and Technology of Nuclear Installations, vol. 2019, 2019, Art. no. 4930274.
14. [14] D. B. Pelowitz, et al. MCNPXTM User's Manual, Version 2.7.0. Los Alamos National Laboratory Tech. Rep. LA-CP-11-00438. Los Alamos, NM, USA, 2011.
15. [15] W. B. Wilson, S. T. Cowell, T. R. England, A. C. Hayes and P. Moller, “A manual for CINDER'90 Version 07.4 codes and data,” Los Alamos National Laboratory report LA-UR-07-8412, Version 07.4.2, 2008.