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Defense › Strategic Isotopes for Defense
Strategic Isotopes for Defense

Tritium Breeding in the Breeder

The breeder (Hyperion) is studied to breed its own tritium in a lithium blanket, with the tritium breeding ratio treated as a design lever across 1.1, 1.5, and 1.8.

Machine
Breeder (Hyperion), D-T spherical tokamak
Breeding medium
Lithium blanket
TBR lever
1.1 / 1.5 / 1.8
Fusion power
85.0 MW

Breeding from lithium

A deuterium-tritium fusion device consumes tritium in the plasma and produces energetic neutrons. Those 14 MeV neutrons can be captured in a surrounding lithium blanket, where reactions on lithium-6 and lithium-7 produce fresh tritium. The figure of merit is the tritium breeding ratio (TBR): tritium bred per tritium burned.

n + ⁶Li → ⁴He + Tthe 14 MeV fusion neutron drives the breeding reactionREACTION
Neutron capture on lithium-6 breeds tritium in the blanket.

In the Kronos studies the TBR is treated as a design lever rather than a single fixed number, and is examined across values of 1.1, 1.5, and 1.8. A TBR above 1 is what makes self-sufficiency, and a surplus for external supply, physically possible. The three values bracket a range from bare self-sufficiency toward a meaningful export surplus.

Self-sufficiency versus surplus

A TBR near 1.1 aims at replacing what the plasma burns plus modest losses. Higher values (1.5, 1.8) open the possibility of a net surplus that could serve external demand — the tritium-class output on the order of ~4 kg/yr referenced in the design set. Which value is achievable in hardware is exactly the kind of question that remains open until the machine is built and measured.

RELATIVE SCALE TBR 1.8 (study upper)largest breeding surplusTBR 1.5 (study mid)surplus caseTBR 1.1 (study lower)near self-sufficiency
TBR is a lever, not a measurement; higher TBR widens the potential surplus.

Neutron economy sets the ceiling

The achievable breeding ratio is ultimately a neutron-economy problem. Each fusion neutron can breed at most a limited amount of tritium, and neutrons are lost to structure, ports, diagnostics, and parasitic absorption before they reach lithium. Neutron-multiplying materials in the blanket can recover some of that loss, but coverage is never complete because the machine needs openings. This is why a target such as 1.8 is treated as an upper study value rather than a promise: closing the gap between an idealized blanket and a real one with penetrations is exactly the engineering work the program flags as open.

Reconciling the achievable TBR with realistic blanket coverage and losses is an active engineering question in the breeder program, and is reported honestly as a design target rather than a delivered result.

Honest gateTBR is treated as a design lever (1.1/1.5/1.8) in simulation. The breeder (Hyperion) is a design and simulation study. Construction begins Q2 2027; first-of-a-kind (FOAK) first tritium is targeted for ~2030. No hardware net-gain or delivered-isotope claim is made before FOAK.
Content reviewed August 2026 · design-and-simulation stage