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Neutronics Analysis in Support of the Fusion Development Facility Design Evolution

M. E. Sawan, A. M. Ibrahim, P. P. H. Wilson, E. P. Marriott, R. D. Stambaugh, C. P. C. Wong

Fusion Science and Technology / Volume 60 / Number 2 / August 2011 / Pages 671-675

Nuclear Analysis & Experiments / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2)

3-D neutronics analysis was performed for the baseline design of FDF. Two blanket concepts were considered; Dual Coolant Lead Lithium (DCLL), and Helium Cooled Ceramic Breeder (HCCB). A peak outboard neutron wall loading of 2 MW/m2 and a fluence of 6 MW-yr/m2 can be achieved with 240 MW fusion power. The tritium breeding ratio is adequate for both blankets. Modest magnet damage parameters were obtained. However, it is recommended that the PF coil in the divertor region be moved vertically farther from the mid-plane to allow adding ~15 cm of shield to reduce the peak organic insulator dose to an acceptable level.

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