Tritium in the Fuel Cycle of a D-3He Fusion Reactor
Fusion Science and Technology / Volume 22 / Number 1 / August 1992 / Pages 135-137
Technical Paper / D-3He/Fusion Reactor / dx.doi.org/10.13182/FST92-A30063
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Problems related to tritium in the fuel cycle of a D-3He fusion reactor are discussed. About 15 g/day of tritium is estimated to be exhausted from a 1-GW(electric) D-3He reactor. The cumulative amount of tritium in storage reaches ∼80 kg after 30 yr of operation if all the tritium exhausted from the plasma is confined.
