Design of an experimental facility to study convection in liquid lithium

M. A. Jaworski, D. N. Ruzic

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

Liquid lithium has been proposed as a possible material for both the first wall and the divertor/limiter of a fusion device. Recent experiments on the CDX-U device show that lithium can absorb a surface heat flux of greater than 40(MW/m2) with negligible evaporation. Observation of a focused electron beam hitting solid lithium in the CDX-U lithium tray saw melting of a large section and induced flows. It is believed that these flows redistributed the incident power flux. This paper presents the design of an experiment which will diagnose the flows induced by an intense heat flux onto a lithium pool and measure the maximum heat flux lithium can absorb with applied magnetic fields. A simplified analytical treatment of the expected fluid flow magnitude with increasing magnetic field and surface thermal gradient is shown. Experimental results of the system electron beam source are also shown. These results are the first step in the creation of an experimental facility to study the heat transfer capabilities of free-surface liquid lithium at the University of Illinois.

Original languageEnglish (US)
Title of host publicationProceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07
DOIs
StatePublished - Dec 1 2007
Event22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07 - Albuquerque, NM, United States
Duration: Jun 17 2007Jun 21 2007

Publication series

NameProceedings - Symposium on Fusion Engineering

Other

Other22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07
CountryUnited States
CityAlbuquerque, NM
Period6/17/076/21/07

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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  • Cite this

    Jaworski, M. A., & Ruzic, D. N. (2007). Design of an experimental facility to study convection in liquid lithium. In Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07 [4337874] (Proceedings - Symposium on Fusion Engineering). https://doi.org/10.1109/FUSION.2007.4337874