Breeder blanket and tritium fuel cycle feasibility of the Infinity Two fusion pilot plant

The selection, design and optimization of a suitable blanket configuration for an advanced high-field stellarator concept is seen as a key feasibility issue and has been incorporated as a vital and necessary part of the Infinity Two fusion pilot plant physics basis. The focus of this work was to identify a baseline blanket which can be rapidly deployed for Infinity Two while also maintaining flexibility and opportunities for higher performing concepts later in development. Results from this analysis indicate that gas-cooled solid breeder designs such as the helium-cooled pebble bed (HCPB) are the most promising concepts, primarily motivated by the neutronics performance at applicable blanket build depths, and the relatively mature technology basis. The lithium lead (PbLi) family of concepts, particularly the dual-cooled lithium lead, offer a compelling alternative to solid blanket concepts as they have synergistic developmental pathways while simultaneously mitigating much of the technical risk of those designs. Homogenized three-dimensional neutronics analysis of the Infinity Two configuration indicates that the HCPB achieves an adequate tritium breeding ratio (TBR) (1.30 which enables sufficient margin at low engineering fidelity), and near appropriate shielding of the magnets (average fast fluence of 1.3 ${\times}$ 10 $^{18}$ n cm $^{-2}$ per full-power year). The thermal analysis indicates that reasonably high thermal efficiencies (greater than 30 %) are readily achievable with the HCPB paired with a simple Rankine cycle using reheat. Finally, the tritium fuel cycle analysis for Infinity Two shows viability, with anticipated operational inventories of less than one kilogram (approximately 675 g) and a required TBR (TBR $_{\textrm {req}}$ ) of less than 1.05 to maintain fuel self-sufficiency (approximately 1.023 for a driver blanket with no inventory doubling). Although further optimization and engineering design are still required, at the physics basis stage all initial targets have been met for the Infinity Two configuration.

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Publication Details

Journal
Journal of Plasma Physics
Published
2025-03-24
DOI
https://doi.org/10.1017/s002237782500039x
Citations
7
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
34.95
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article

Breeder blanket and tritium fuel cycle feasibility of the Infinity Two fusion pilot plant

L. Singh, Boon Tong Goh, M. S. Tillack, Noah Mandell et al.
7 citations
Journal of Plasma Physics
Nuclear reactor physics and engineering
34.95
article

Breeder blanket and tritium fuel cycle feasibility of the Infinity Two fusion pilot plant

L. Singh, Boon Tong Goh, M. S. Tillack, Noah Mandell, S. Ramirez, W. Guttenfelder, C. Lau, J.C. Schmitt, Antoine Cerfon, Paul Wilson, C. Moreno, Tim D. Bohm, J. M. Canik, Jonas Kessing, D. Clark, E. Pflug, J. Smandych
article en
7 citations

Abstract

The selection, design and optimization of a suitable blanket configuration for an advanced high-field stellarator concept is seen as a key feasibility issue and has been incorporated as a vital and necessary part of the Infinity Two fusion pilot plant physics basis. The focus of this work was to identify a baseline blanket which can be rapidly deployed for Infinity Two while also maintaining flexibility and opportunities for higher performing concepts later in development. Results from this analysis indicate that gas-cooled solid breeder designs such as the helium-cooled pebble bed (HCPB) are the most promising concepts, primarily motivated by the neutronics performance at applicable blanket build depths, and the relatively mature technology basis. The lithium lead (PbLi) family of concepts, particularly the dual-cooled lithium lead, offer a compelling alternative to solid blanket concepts as they have synergistic developmental pathways while simultaneously mitigating much of the technical risk of those designs. Homogenized three-dimensional neutronics analysis of the Infinity Two configuration indicates that the HCPB achieves an adequate tritium breeding ratio (TBR) (1.30 which enables sufficient margin at low engineering fidelity), and near appropriate shielding of the magnets (average fast fluence of 1.3 ${\times}$ 10 $^{18}$ n cm $^{-2}$ per full-power year). The thermal analysis indicates that reasonably high thermal efficiencies (greater than 30 %) are readily achievable with the HCPB paired with a simple Rankine cycle using reheat. Finally, the tritium fuel cycle analysis for Infinity Two shows viability, with anticipated operational inventories of less than one kilogram (approximately 675 g) and a required TBR (TBR $_{\textrm {req}}$ ) of less than 1.05 to maintain fuel self-sufficiency (approximately 1.023 for a driver blanket with no inventory doubling). Although further optimization and engineering design are still required, at the physics basis stage all initial targets have been met for the Infinity Two configuration.

Journal of Plasma PhysicsVol. 91(3)
Capital One (United States) (US), University of Wisconsin–Madison (US)
Affordable and clean energy
Openalex Percentile: Top 0%
Nuclear reactor physics and engineering
34.95
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