Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 60 / Number 2 / Pages 533-537
B. G. Hong, J. H. Seo
Fusion Science and Technology / Volume 60 / Number 2 / Pages 533-537
Format:electronic copy (download)
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.
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