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Safety Aspects of Tritium in ICF Reactors with Internally-Breeding Targets

Magdi Ragheb, George H. Miley

Fusion Science and Technology / Volume 8 / Number 2P2 / September 1985 / Pages 2061-2066

Fusion Reactor / Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) / dx.doi.org/10.13182/FST85-A24588

The LOTRIT inertial confinement reactor concept employs a deuterium burning target with a DT spark trigger core. This eliminates the need for tritium breeding in a blanket, and leads to a minimization of the tritium inventory and of the possibility of metal fire hazards if lead is used instead of lithium for first wall protection. The active fuel inventory in the fuel cycle and blanket per MJ of energy produced is only 5 percent of the DT case. The most significant reduction in the total tritium inventory is in the target manufacture and storage areas, and is about 1.8% of the DT case per unit of fusion energy produced. If the goal is to reduce the risk from tritium releases from fusion reactors to below that of fission reactors, it is estimated that the tritium releases must be maintained at 0.13–5.0 Ci/day. Attaining these values will be costly, technologically difficult and will constrain the design options in DT-based systems, but may be within the realm of systems using the LOTRIT concept.