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Tritium breeding in a fusion--fission hybrid breeder reactor

Technical Report ·
DOI:https://doi.org/10.2172/6531756· OSTI ID:6531756
In order to construct a D-T fusion-fission hybrid breeder reactor there must be some guarantee that tritium will be available to fuel the fusion reaction. This can be achieved by breeding tritium in the blanket of the reactor. A variety of blanket configurations have been studied with the intent of arriving at a blanket design capable of attaining sizeable values of power and fissile fuel production, and simultaneously assure self-sufficiency in tritium production for the reactor, i.e., a T-breeding ratio greater than 1.0. Using a four group diffusion theory code, a number of possible blanket configurations were studied during the parametric phase of hybrid breeder blanket design. They included tritium breeding zones of natural or enriched lithium metal and natural lithium in dilithium oxide, neutron multiplier zones of uranium and thorium with varying amounts of plutonium, thorium fissile breeding zones (sometimes containing plutonium), and graphite reflector zones. The choice of clad used in the fuel rods has also been found to influence tritium breeding. One of the more promising designs studied combines a tritium breeding ratio of 1.2 with a blanket fissile power of 16 GW(th), and a U-233 production rate of 2.7 tonnes per year.
Research Organization:
Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.; Pennsylvania State Univ., University Park (USA)
OSTI ID:
6531756
Report Number(s):
WFPS-TME-090
Country of Publication:
United States
Language:
English