Modeling and analysis of the tritium fuel cycle for ARC- and STEP-class D-T fusion power plants

Meschini, Samuele; Ferry, Sara E.; Delaporte-Mathurin, Rémi; Whyte, Dennis G.

doi:10.1088/1741-4326/acf3fc

Modeling and analysis of the tritium fuel cycle for ARC- and STEP-class D-T fusion power plants

Journal Article · Thu Sep 14 00:00:00 EDT 2023 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/acf3fc· OSTI ID:2000085

; ; ; Whyte, Dennis G.

Abstract

The limited tritium resources available for the first fusion power plants (FPPs) make fuel self-sufficiency and tritium inventory minimization leading issues in FPP design. This work builds on the model proposed by Abdou et al (2020 Nucl. Fusion 61 013001), which analyzed the fuel cycle (FC) of a DEMOnstration nuclear FPP-class FPP with a time-dependent system-level model. Here, we use a modified version of their model to analyze the FC of an Affordable, Robust, Compact (ARC)-class tokamak and two versions of a Spherical Tokamak for Energy Production (STEP)-class tokamak. The ARC-class tokamak breeds tritium in a 2LiF + BeF ₂ liquid immersion blanket, while the STEP-class tokamak breeds tritium utilizing either a liquid-lithium blanket design or an encapsulated breeding blanket. A time-dependent system-level model is developed in Matlab Simulink ^® to simulate the evolution of tritium flows and tritium inventories in the FC. The main goals of this work are to assess tritium self-sufficiency of the ARC- and STEP-class designs and to determine quantitative design requirements that can be used to analyze the adequacy of a proposed FC system. These design requirements are aimed at achieving a low tritium inventory doubling time ( $t_{d}$ ) and a low start-up inventory ( $I_{s t a r t u p}$ ) while keeping the required tritium breeding ratio (TBR $_{r}$ ) as low as possible. We also consider how improvements in FC technology and POs affect TBR $_{r}$ and $I_{s t a r t u p}$ . The model results show that TBR $_{r}$ for ARC- and STEP-class FPPs should be achievable if the tritium burn efficiency (TBE) reaches 0.5%–1% (TBR $_{r} <$ 1.2). This assumes significant, but attainable, improvements over current abilities. However, the model results indicate that an FPP must achieve ambitious performance targets, including FPP availability $>$ 70%, tritium processing time $<$ 4 h, and the implementation of direct internal recycling (DIR). If future research yields major improvements to achievable TBE, it may be possible to achieve tritium self-sufficiency while operating at lower availability and without implementing DIR.

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Sponsoring Organization:: USDOE Advanced Research Projects Agency - Energy (ARPA-E)

Grant/Contract Number:: AR0001542

OSTI ID:: 2000085

Alternate ID(s):: OSTI ID: 1996841
OSTI ID: 2578805

Journal Information:: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 12 Vol. 63; ISSN 0029-5515

Publisher:: IOP PublishingCopyright Statement

Country of Publication:: IAEA

Language:: English

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