Preprint / Version 1

Optimization of Tokamak Blanket Design to Minimize Neutron Flux on Magnets

##article.authors##

  • Steven Benny Polygence

DOI:

https://doi.org/10.58445/rars.1264

Keywords:

Tokamak Blanket Design, Neutron Flux, Magnets

Abstract

Fusion energy, a promising solution to global energy challenges, replicates the same processes that give our sun its energy, notably through deuterium-tritium (D-T) fusion reactions that produce significant energy. This study explores the mechanics and challenges of various fusion reactions, emphasizing the pivotal role of lithium breeder blankets in producing tritium, essential for sustaining D-T fusion in tokamak reactors. The helium-cooled lithium lead (LiPb) blanket design was simulated to optimize tritium breeding and neutron flux management. Results indicated a tritium breeding ratio (TBR) of 1.15, surpassing the self-sufficiency target of 1.1, with further improvements through increased lithium content and blanket thickness. Effective neutron shielding ensured safe operational limits for reactor components. These findings demonstrate the feasibility of achieving self-sustaining fusion reactions, essential for the viability of fusion power as a sustainable energy source. Future research will focus on advanced materials, refined simulations, and enhanced cooling technologies to further optimize fusion reactor designs.

References

Hupin, G., Quaglioni, S., & Navrátil, P. "Ab initio predictions for polarized deuterium-tritium thermonuclear fusion." *Nature Communications*, vol. 10, 2019, p. 351, doi:10.1038/s41467-018-08052-6.

Eliezer, S., et al. "Title of the Article." *Journal Name*, vol. 40, 2000, pp. 195.

Mahdavi, M., & Kaleji, B. "Deuterium/helium-3 fusion reactors with lithium seeding." *Plasma Physics and Controlled Fusion*, vol. 51, no. 8, 2009, pp. 085003.

Asaoka, Yoshiyuki, et al. "Requirements of tritium breeding ratio for early fusion power reactors." *Fusion Technology*, vol. 30, no. 3P2A, 1996, pp. 853-863.

Kuroda, T., et al. "Technical considerations on tritium breeding blanket systems for a fusion power reactor." *Fusion Engineering and Design*, vol. 8, 1989, pp. 219-226, doi:10.1016/S0920-3796(89)80110-3.

Judd, W. C., Dutina, D., & Rodden, C. J. *Reactor Coolants*. Nuclear Materials and Equipment Corp., 1964.

Demange, D., et al. "Tritium extraction technologies and DEMO requirements." *Fusion Engineering and Design*, vol. 109, 2016, pp. 912-916.

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Posted

2024-07-06

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