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- W349553485 abstract "AbstractThe potential of moderated and fast hybrid blankets is investigated for the rejuvenation of CANDU spent fuel. The moderated hybrid blanket has revealed poor neutronic performance and is not suitable for CANDU spent-fuel rejuvenation. The fast-fissioning hybrid blanket has excellent neutronic performance and is investigated to achieve different enrichment grades of fissile isotopes (EGFI) for three different applications:1. recycling in a conventional commercial CANDU reactor (EGFI = 0.71 to 0.9%)2. recycling in an advanced CANDU reactor concept with high burnup rate (EGFI = 1%)3. recycling in an advanced breeder with thorium fuel (EGFI > 1.5%)For fast-fissioning blankets, a rejuvenation period of up to 24 months is investigated by a plant factor of 75% under a first-wall (deuterium, tritium) fusion neutron current load of 1014 to 14 MeV·n/cm2·s, corresponding to 2.25 MW/m2.Rejuvenation periods of 6 to 12 months, 10 to 16 months, and 18 months, respectively, are evaluated for the above-mentioned re..." @default.
- W349553485 created "2016-06-24" @default.
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- W349553485 date "1989-11-01" @default.
- W349553485 modified "2023-10-18" @default.
- W349553485 title "Investigation of the Neutronic Potential of Moderated and Fast (D,T) Hybrid Blankets for Rejuvenation of CANDU Spent Fuel" @default.
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- W349553485 doi "https://doi.org/10.13182/fst89-a29125" @default.
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