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Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector.

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Bibliographic Details
Title: Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector.
Authors: Barker, Adam J.1 (AUTHOR) adam.barker-3@manchester.ac.uk, Gilbert, Mark R.2 (AUTHOR), Edmondson, Philip D.1 (AUTHOR)
Source: Nuclear Fusion. Aug2025, Vol. 65 Issue 8, p1-12. 12p.
Subjects: Tritium, Fusion reactor blankets, Neutron flux, Fusion reactors, Neutron reflectivity, Fused salts
Abstract: Tritium production in a fusion reactor is essential for a deuterium-tritium burning plasma source, and designing a lithium-containing breeder blanket is crucial for a closed fuel cycle in an electricity-to-grid power plant. Tritium is a rare resource, currently produced only in a limited number of fission reactors and other low-output facilities. Due to the lack of experimental data in this area, neutronics calculations will guide the design of the first-generation fusion blankets tasked with tritium fuel production as without maximised breeding potential, reactor startup times may need to be postponed due to a low global inventory. This paper describes an optimisation workflow that segments a DEMO-style blanket to allow flexibility in material allocation, along with the necessary validation steps for repeatable results. The developed blanket is tested within the neutronics code OpenMC to evaluate the performance of a hybrid liquid metal–molten salt breeder. FLiBe is found to be an efficient neutron reflector, showing performance increases of 7%, resulting in an overall tritium breeding ratio (TBR) of 1.11, even with a natural abundance of 7.5 % lithium-6. Analysis of the neutron spectral profile indicates a shift towards thermal neutrons when reflected from FLiBe placed at the rear of the design. The use of molten salt as a reflector is novel as a result of its ability to breed tritium and provide a secondary increase in TBR through the reflection of neutrons. A dual system would require more complex engineering, but may offer a solution for compact reactors and/or systems with low lithium enrichment. [ABSTRACT FROM AUTHOR]
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Abstract:Tritium production in a fusion reactor is essential for a deuterium-tritium burning plasma source, and designing a lithium-containing breeder blanket is crucial for a closed fuel cycle in an electricity-to-grid power plant. Tritium is a rare resource, currently produced only in a limited number of fission reactors and other low-output facilities. Due to the lack of experimental data in this area, neutronics calculations will guide the design of the first-generation fusion blankets tasked with tritium fuel production as without maximised breeding potential, reactor startup times may need to be postponed due to a low global inventory. This paper describes an optimisation workflow that segments a DEMO-style blanket to allow flexibility in material allocation, along with the necessary validation steps for repeatable results. The developed blanket is tested within the neutronics code OpenMC to evaluate the performance of a hybrid liquid metal–molten salt breeder. FLiBe is found to be an efficient neutron reflector, showing performance increases of 7%, resulting in an overall tritium breeding ratio (TBR) of 1.11, even with a natural abundance of 7.5 % lithium-6. Analysis of the neutron spectral profile indicates a shift towards thermal neutrons when reflected from FLiBe placed at the rear of the design. The use of molten salt as a reflector is novel as a result of its ability to breed tritium and provide a secondary increase in TBR through the reflection of neutrons. A dual system would require more complex engineering, but may offer a solution for compact reactors and/or systems with low lithium enrichment. [ABSTRACT FROM AUTHOR]
ISSN:00295515
DOI:10.1088/1741-4326/adecb2