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A Computer Code for Tokamak Reactor Concepts Evaluation

F. Rosatelli, G. Raia

Fusion Science and Technology / Volume 8 / Number 1P2A / July 1985 / Pages 362-366

Power Reactor and Next-Generation Studies / Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) / dx.doi.org/10.13182/FST85-A40071

A computer package has been developed which could preliminarely investigate the engineering configuration of a tokamak reactor concept. Therefore the code is essentially intended to synthetize, starting from a set of geometrical and plasma physics parameters and the required performances and objectives, three fundamental components of a tokamak reactor core: blanket+shield, TF magnet, PF magnet. An iterative evaluation of the size, power supply and cooling system requirements of these components allows the judgment and the preliminary design optimization on the considered reactor concept. The versatility of the code allows its application both to next generation tokamak devices and power reactor concepts.