Nuclear Engineering and Technology (Apr 2022)

Densification of matrix graphite for spherical fuel elements used in molten salt reactor via addition of green pitch coke

  • Zhao He,
  • Hongchao Zhao,
  • Jinliang Song,
  • Xiaohui Guo,
  • Zhanjun Liu,
  • Yajuan Zhong,
  • T. James Marrow

Journal volume & issue
Vol. 54, no. 4
pp. 1161 – 1166

Abstract

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Green pitch coke with an average particle size of 2 μm was adopted as densifier and added to the raw materials of conventional A3-3 matrix graphite (MG) to prepare modified A3-3 matrix graphite (MMG) by the quasi-isostatic molding method. The structure, mechanical and thermal properties were assessed. Compared with MG, MMG had a more compact structure, and exhibited improved properties of higher mechanical strength, higher thermal conductivity and better molten salt barrier performance. Notably, under the same infiltration pressure of 5 atm, the fluoride salt occupation of MMG was only 0.26 wt%, whereas it was 15.82 wt% for MG. The densification effect of green pitch coke endowed MMG with improved properties for potential use in the spherical fuel elements of molten salt reactor.

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