Design integration of liquid surface divertors

R. E. Nygren, D. F. Cowgill, M. A. Ulrickson, B. E. Nelson, P. J. Fogarty, T. D. Rognlien, M. E. Rensink, A. Hassancin, S. S. Smolentsev, M. Kotschenreuther

Research output: Contribution to journalArticlepeer-review

24 Scopus citations

Abstract

The US Enabling Technology Program in fusion is investigating the use of free flowing liquid surfaces facing the plasma. We have been studying the issues in integrating a liquid surface divertor into a configuration based upon an advanced tokamak, specifically the ARIES-RS configuration. The simplest form of such a divertor is to extend the flow of the liquid first wall into the divertor and thereby avoid introducing additional fluid streams. In this case, one can modify the flow above the divertor to enhance thermal mixing. For divertors with flowing liquid metals (or other electrically conductive fluids) MHD (magneto-hydrodynamics) effects are a major concern and can produce forces that redirect flow and suppress turbulence. An evaluation of Flibe (a molten salt) as a working fluid was done to assess a case in which the MHD forces could be largely neglected. Initial studies indicate that, for a tokamak with high power density, an integrated Flibe first wall and divertor does not seem workable. We have continued work with molten salts and replaced Flibe with Flinabe, a mixture of lithium, sodium and beryllium fluorides, that has some potential because of its lower melting temperature. Sn and Sn-Li have also been considered, and the initial evaluations on heat removal with minimal plasma contamination show promise, although the complicated 3D MHD flows cannot yet be fully modeled. Particle pumping in these design concepts is accomplished by conventional means (ports and pumps). However, trapping of hydrogen in these flowing liquids seems plausible and novel concepts for entrapping helium are also being studied.

Original languageEnglish
Pages (from-to)223-244
Number of pages22
JournalFusion Engineering and Design
Volume72
Issue number1-3 SPEC. ISS.
DOIs
StatePublished - Nov 2004
Externally publishedYes

Funding

A goal of the APEX and ALPS Programs in the US is to investigate the potential for the use of free liquid surfaces in fusion chamber technology and to do so with a sufficient level of effort that the design issues can be resolved and an accurate assessment of this potential can be understood. In this work, we are supported by the APEX and ALPS Teams and a significant programmatic commitment by the Department of Energy's US Fusion Energy Science Program has enabled us to utilize diverse expertise in plasma edge modeling, advanced mechanical and systems design, and heat transfer. Although still in the early phase of developing liquid surface concepts, we have made significant progress in identifying useful coolants, divertor geometries and plasma edge conditions. The work of two authors (TDR and MER) was performed under the auspices of the U.S. Department of Energy by contract W-7405-Eng-48 at the University of California Lawrence Livermore National Laboratory.

FundersFunder number
U.S. Department of EnergyW-7405-Eng-48
Lawrence Livermore National Laboratory

    Keywords

    • Divertor
    • Edge modeling
    • First wall

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