Nuclear Engineering and Technology (May 2021)

Mesocarbon microbead densified matrix graphite A3-3 for fuel elements in molten salt reactors

  • Haoran Wang,
  • Liujun Xu,
  • Yajuan Zhong,
  • Xiaoyun Li,
  • Hui Tang,
  • Feng Zhang,
  • Xu Yang,
  • Jun Lin,
  • Zhiyong Zhu,
  • Yan You,
  • Junqiang Lu,
  • Libing Zhu

Journal volume & issue
Vol. 53, no. 5
pp. 1569 – 1579

Abstract

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This study aims to provide microstructural characterization for the matrix graphite which molten salt reactors (MSRs) use, and improve resistance to molten salt infiltration of the matrix graphite for fuel elements. Mesocarbon microbeads (MCMB) densified matrix graphite A3-3 (MDG) was prepared by a quasi-isostatic pressure process. After densification by MCMBs with average particle sizes of 2, 10, and 16 μm, the pore diameter of A3-3 decreased from 924 nm to 484 nm, 532 nm, and 778 nm, respectively. Through scanning electron microscopy, the cross-section energy spectrum and time-of-flight secondary ion mass spectrometry, resistance levels of the matrix graphite to molten salt infiltration were analyzed. The results demonstrate that adding a certain proportion of MCMB powders can improve the anti-infiltration ability of A3-3. Meanwhile, the closer the particle size of MCMB is to the pore diameter of A3-3, the smaller the average pore diameter of MDG and the greater the densification. As a matrix graphite of fuel elements in MSR was involved, the thermal and mechanical properties of matrix graphite MDG were also studied. When densified by the MCMB matrix graphite, MDGs can meet the molten salt anti-infiltration requirements for MSR operation.

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