Tritium production and processing systems for ST-E1
Emrah Yıldırım; J. Naish; J. Trueba; Samara M. Levine; Abhishek Kumar; V.B. Gohani; M.K.E. Mohamed; Anatoliy Vorobev · 2026 · Nuclear Fusion
WASTE classifies this as Negative / Null Result Report · AI classification, approximate
The study found no significant effect — useful as a negative control or null benchmark for your own design.
Abstract
Abstract An integrated tritium fuel-cycle architecture has been developed for ST-E1, a low-aspect-ratio, high-power fusion power plant. The approach couples a helium-cooled liquid-lithium breeder blanket with a dedicated circulation loop providing tritium extraction, heat removal, and inventory control within a unified system boundary. Downstream of the blanket, the tritium processing system comprises of extraction, purification, isotope separation, and storage subsystems sized to accommodate the plant’s dynamic tritium production and consumption rates. Inventory modelling is used to assess ca
Abstract by Emrah Yıldırım; J. Naish; J. Trueba; Samara M. Levine; Abhishek Kumar; V.B. Gohani; M.K.E. Mohamed; Anatoliy Vorobev, Nuclear Fusion (2026) — licensed CC BY 4.0.
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Metadata source: OpenAlex · DOI 10.1088/1741-4326/ae773a