A Tokamak Tritium Production Reactor Design II
| Autor: | G. Y. Poe, S. Klima, A. O. Rodriguez, R. D. Jeffcoat, R. T. Still, T. A. Deterding, D. D. Thomas, M. T. McLain, E. M. Fort, J. P. Aldridge, J. G. Evans, Weston M. Stacey, R. L. Beilke, A. D. Nielsen, B. H. Rose, L. G. Bryson, E. P. Davidson, M. J. O’Neill, G. M. Roach, M. P. Valenzano, H. U. Rehman |
|---|---|
| Rok vydání: | 1998 |
| Předmět: |
Thermonuclear fusion
Tokamak 020209 energy Nuclear engineering General Engineering Radioactive waste 02 engineering and technology Fusion power 01 natural sciences Nuclear decommissioning 010305 fluids & plasmas Coolant law.invention Nuclear physics Breeder (animal) law 0103 physical sciences 0202 electrical engineering electronic engineering information engineering Tritium |
| Zdroj: | Fusion Technology. 33:443-455 |
| ISSN: | 0748-1896 |
| DOI: | 10.13182/fst98-a43 |
| Popis: | 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. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|