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- W601772615 abstract "To determine the radial build of tokamak reactor systems, a one-dimensional radiation transport code is coupled with the system analysis. Neutronic effects such as the tritium breeding capability and the shielding characteristics are self-consistently calculated in the system analysis which allows a determination of the design parameters of a reactor which satisfy plasma physics and engineering constraints simultaneously. We apply this coupled analysis to determine the radial build of tokamak reactor systems and show that it is a powerful tool for the optimal design of a tokamak reactor." @default.
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- W601772615 date "2011-08-01" @default.
- W601772615 modified "2023-09-26" @default.
- W601772615 title "Impact of Neutronics on the Determination of a Radial Build of Tokamak Reactor Systems" @default.
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- W601772615 doi "https://doi.org/10.13182/fst11-a12437" @default.
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