Published June 2011 | Version v1
Journal article

Preliminary three-dimensional neutronics design and analysis of helium-cooled blanket for a multi-functional experimental fusion-fission hybrid reactor

  • 1. School of Nuclear Science and Technology, University of Science and Technology of China, Hefei (China)
  • 2. Institute of Plasma Physics, China Academy of Sciences, Hefei (China)

Description

A multi-functional experimental fusion-fission hybrid reactor concept named FDS-MFX, which is based on viable fusion and fission technologies, has been proposed. Three-stage tests will be carried out successively, in which the tritium breeding blanket, uranium-fueled blanket and spent-fuel-fueled blanket will be utilized respectively. In this paper, the design optimization for the layout and the size of high enriched uranium modules in later stage of uranium-fueled blanket has been performed. Finally, proposing a preliminary three-dimension neutronics design with maximum average Power Density (PDmax) 100 MW/ m3, loaded mass of the 235U 1000 kg and TBR (Tritium Breeding Ratio) 1.05. (authors)

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
31
Journal Issue
2
Journal Page Range
p. 169-174
ISSN
0258-0918

Optional Information

Notes
6 figs., 2 tabs., 15 refs.