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A Tokamak Tritium Production Reactor Design II

W. M. Stacey, J. P. Aldridge, R. L. Beilke, L. G. Bryson, E. P. Davidson, T. A. Deterding, J. G. Evans, E. M. Fort, R. D. Jeffcoat, S. Klima, M. T. McLain, A. D. Nielsen, M. J. O'Neill, G. Y. Poe, H. U. Rehman, B. H. Rose, G. M. Roach, A. O. Rodriguez, R. T. Still, D. D. Thomas, M. P. Valenzano

Fusion Science and Technology / Volume 33 / Number 4 / July 1998 / Pages 443-455

Technical Paper / dx.doi.org/10.13182/FST98-A43

A design concept for a fusion neutron source-based tritium production reactor has been developed, where liquid Li is used as the coolant and tritium breeder and V-4 Cr-4 Ti is used as the structural material. The fusion neutron source is predicated on the physics and technology that will be demonstrated in the International Thermonuclear Experimental Reactor (ITER). The present design can produce 2 kg/yr excess tritium for weapons replenishment operating at fusion power levels of 300 to 750 MW and with corresponding plant availability factors of 25 to 10%. No structural component should fail as a result of radiation damage during the 40-yr lifetime of the reactor, and it should be possible to dispose of the radioactive waste created upon decommissioning as low-level waste that qualifies for shallow land burial. A fusion tritium production reactor based on ITER physics and technology would seem to be a realistic option for satisfying the nation's tritium production needs.