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- W47513689 abstract "Basic performance analyses of a fast thermionic blanket driven by a deuterium-tritium fusion reactor with a wall loading of 2.25 MW/m/sup 2/ (10/sup 14/ incident neutron/cm/sup 2/s) is discussed. The basic thermionic element has been evaluated with some modifications from the German Incore-Thermionic-Reactor Project. During this study, highly enriched UO/sub 2/ fuel is replaced by the following actinide waste materials: /sup 244/CmO/sub 2/, (/sup 241/AmO/sub 2/ + /sup 243/AmO/sub 2/) corresponding to the isotopic composition of the nuclear waste materials produced in light water reactors, natural UO/sub 2/. The calculated high emitter heating values P for converters with /sup 244/CmO/sub 2/ as nuclear fuel are adequate for efficient thermionic conversion, P > 90 W(thermal)/ cm/sup 2/. Those values with AmO/sub 2/ fuel are also still in the range of interest (P > 40 to 50 W(thermal)/ cm/sup 2/) whereas they are rather low for thermionic hybrid blanket with natural uranium (P = 15 to 20 W(thermal)/cm/sup 2/)." @default.
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- W47513689 date "1984-05-01" @default.
- W47513689 modified "2023-10-18" @default.
- W47513689 title "Fast Hybrid Thermionic Blankets with Actinide Waste Fuel" @default.
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- W47513689 doi "https://doi.org/10.13182/fst84-a23112" @default.
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