Abstract :
This study investigates neutron economy and the thorium fuel cycle within Thorium Molten Salt Reactors to evaluate their potential for sustainable nuclear energy production. Using a Systematic Literature Review (SLR) methodology, this study synthesized recent research published between 2020 and 2026, while also using selected foundational sources from 1960 onward for core nuclear-theory parameters. Data were analyzed using a qualitative and comparative approach, focusing on thorium-232 conversion pathways, uranium-233 production mechanisms, and neutronic performance parameters. The findings indicate that U-233 is a superior fissile fuel for the thorium cycle, exhibiting a high neutron reproduction factor of 2.28 for thermal neutrons and 2.50 for fast neutrons, which supports efficient fuel breeding. The thorium cycle offers significant environmental and security benefits, including a substantial reduction in long-lived transuranic actinides and enhanced proliferation resistance due to the presence of uranium-232, which emits high-energy gamma radiation. Furthermore, TMSR technology provides inherent safety through a negative temperature coefficient and the ability for online fuel processing to remove gaseous fission products.
Unlike previous review studies, this research integrates neutron economy, U-233 purity, breeding ratio, salt chemistry, and reactor safety into a unified conceptual framework, providing a comprehensive analytical perspective for the evaluation of thorium molten salt reactors. The study concludes that while the thorium-uranium cycle is a highly effective alternative for improving neutron efficiency and long-term sustainability, successful commercial deployment depends on achieving U-233 purity levels of approximately 85%. Additionally, further research is required to address remaining challenges in structural materials, salt redox chemistry control, and fuel reprocessing.
Keywords :
Breeding Ratio, Molten Salt Reactors, Neutron Economy, Thorium Fuel Cycle, Uranium-233References :
- Ashraf, O., Rykhlevskii, A., Tikhomirov, G. V., & Huff, K. D. (2020). Strategies for thorium fuel cycle transition in the SD-TMSR. Annals of Nuclear Energy, 148, 107656. https://doi.org/10.1016/j.anucene.2020.107656
- DiLisi, G. A., Hirsch, A., Murray, M., & Rarick, R. (2018). Thorium and Molten Salt Reactors: Essential Questions for Classroom Discussions. The Physics Teacher, 56(4), 253–257. https://doi.org/10.1119/1.5028245
- Doligez, X., Heuer, D., Lucotte, E. M., Ghetta, V., Allibert, M., Delpech, S., & Picard, G. (2008). Thorium Molten Salt Reactor reprocessing unit: Characterization and influence on the core behaviour.
- Dwijayanto, R. A. P., & Harto, A. W. (2024). Comparative Assessment of Molten Salt Reactor Neutronic Performance with Various U-233 Purity. Engineering Journal, 28(5), 15–24. https://doi.org/10.4186/ej.2024.28.5.15
- Heuer, D., Merle-Lucotte, E., Allibert, M., Brovchenko, M., Ghetta, V., & Rubiolo, P. (2014). Towards the thorium fuel cycle with molten salt fast reactors. Annals of Nuclear Energy, 64, 421–429. https://doi.org/10.1016/j.anucene.2013.08.002
- Holcomb, D. D. (2020). MOLTEN SALT REACTOR SAFETY ANALYSIS- A U.S. PERSPECTIVE.
- Jeong, C. J., & Park, C. J. (2006). Dynamic Analysis of the Thorium Fuel Cycle in CANDU Reactors (Technical Report KAERI/TR-3148/2006; KAERI Technical Report Series). Korea Atomic Energy Research Institute (KAERI).
- Kang, J., & Von Hippel, F. N. (2001). U‐232 and the proliferation‐resistance of U‐233 in spent fuel. Science & Global Security, 9(1), 1–32. https://doi.org/10.1080/08929880108426485
- Kaygisiz, S. Y. (2023). NEUTRONIC ANALYSIS OF THORIUM-BASED MOLTEN SALT REACTOR.
- (1966). Introduction To Nuclear Reactor Theory | PDF | Nuclear Energy | Nuclear Physics. https://www.scribd.com/document/212575672/John-R-Lamarsh-Introduction-to-Nuclear-Reactor-Theory
- Liverhant, S. E. (1960). Elementary introduction to nuclear reactor physics.
- National Nuclear Laboratory. (2010). The thorium fuel cycle.
- (2015). Introduction of Thorium in the Nuclear Fuel Cycle. OECD Publishing. https://doi.org/10.1787/9789264241732-en
- Puthiyavinayagam, P. (2009). Fast Reactor Core Design Module 2: Core Neutronics.
- Reuss, P. (2020). Neutron physics. EDP Sciences. https://doi.org/10.1051/978-2-7598-0041-4
- Serp, J., Allibert, M., Beneš, O., Delpech, S., Feynberg, O., Ghetta, V., Heuer, D., Holcomb, D., Ignatiev, V., Kloosterman, J. L., Luzzi, L., Merle-Lucotte, E., Uhlíř, J., Yoshioka, R., & Zhimin, D. (2014). The molten salt reactor (MSR) in generation IV: Overview and perspectives. Progress in Nuclear Energy, 77, 308–319. https://doi.org/10.1016/j.pnucene.2014.02.014
- Tsoulfanidis, N., & Landsberger, S. (2010). Measurement and detection of radiation / Nicholas Tsoulfanidis, Sheldon Landsberger. CRC Press. Boca Rato, FL. https://e-bib-fe.extra.cea.fr/Default/doc/SYRACUSE/37720/measurement-and-detection-of-radiation-nicholas-tsoulfanidis-sheldon-landsberger
- Yang, P., Lin, Z.-K., Wan, W., Zhu, G.-F., Yu, X.-H., & Dai, Z.-M. (2020). Preliminary neutron study of a thorium-based molten salt energy amplifier. Nuclear Science and Techniques, 31(4), 41. https://doi.org/10.1007/s41365-020-0750-8
- Zhang, Y.-P., Ma, Y.-W., Wu, J.-H., Chen, J.-G., & Cai, X.-Z. (2020). Preliminary analysis of fuel cycle performance for a small modular heavy water-moderated thorium molten salt reactor. Nuclear Science and Techniques, 31(11), 108. https://doi.org/10.1007/s41365-020-00823-5

