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Impact of Neutronics on the Determination of a Radial Build of Tokamak Reactor Systems

B. G. Hong, J. H. Seo

Fusion Science and Technology / Volume 60 / Number 2 / August 2011 / Pages 533-537

Blanket Design and Experiments / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2)

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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