Power handling of a liquid-metal based CPS structure under high steady-state heat and particle fluxes

T.W. Morgan, A. Vertkov, K. Bystrov, I. Lyublinski, J.W. Genuit, G. Mazzitelli

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13 Citations (Scopus)

Abstract

Liquid metal infused capillary porous structures (CPSs) are considered as a potential divertor solution for DEMO due to their potential power handling capability and resilience to long term damage. In this work the power handling and performance of such Sn-based CPS systems is assessed both experimentally and via modelling. A Sn-CPS target was exposed to heat fluxes of up to 18.1 MW m−2in He plasma in the Pilot-PSI linear device. Post-mortem the target showed no damage to nor any surface exposure of the underlying W-CPS felt. The small pore size (∼40 µm) employed resulted in no droplet formation from the target in agreement with calculated Rayleigh-Taylor and Kelvin-Helmoholtz instability thresholds. The temperature response of the Sn-target was used to determine the thermal conductivity of the mixed Sn-CPS material using COMSOL modelling. These values were then used via further finite element analysis to extrapolate to DEMO relevant monoblock designs and estimate the maximum power handling achievable based on estimated temperature windows for all component elements of the design. For an optimized design a heat-load of up to 20 MW m−2may be received while the use of CPS also offers other potential design advantages such as the removal of interlayer requirements.
Original languageEnglish
Pages (from-to)210 - 215
Number of pages6
JournalNuclear Materials and Energy
Volume12
DOIs
Publication statusPublished - 1 Aug 2017
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science (miscellaneous)
  • Nuclear Energy and Engineering

Cite this

Morgan, T. W., Vertkov, A., Bystrov, K., Lyublinski, I., Genuit, J. W., & Mazzitelli, G. (2017). Power handling of a liquid-metal based CPS structure under high steady-state heat and particle fluxes. Nuclear Materials and Energy, 12, 210 - 215. https://doi.org/10.1016/j.nme.2017.01.017