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

Research output: Contribution to journalArticlepeer-review

7 Scopus citations

Abstract

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.

Original languageEnglish
Pages (from-to)671-675
Number of pages5
JournalFusion Science and Technology
Volume60
Issue number2
DOIs
StatePublished - Aug 2011
Externally publishedYes

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