Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element

Clark, Emily; Lumsdaine, Arnold; Boscary, Jean; Greuner, Henri; Ekici, Kivanc

doi:10.1016/j.fusengdes.2017.07.014

Title: Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element

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Abstract

The long-pulse operation of the Wendelstein 7-X (W7-X) stellarator experiment is scheduled to begin in 2020. This operational phase will be equipped with water-cooled plasma facing components to allow for longer pulse durations. Certain simulated plasma scenarios have been shown to produce heat fluxes that surpass the technological limits on the edges of the divertor target elements during steady-state operation. In order to reduce the heat load on the target elements, the addition of a “scraper element” (SE) is under investigation. The SE is composed of 24 water-cooled carbon fiber reinforced carbon composite monoblock units. Multiple full-scale prototypes have been tested in the GLADIS high heat flux test facility. Previous computational studies revealed discrepancies between the simulations and experimental measurements. In this work, single-phase thermal-hydraulics modeling was performed in ANSYS CFX to identify potential causes for such discrepancies. Possible explanations investigated were the effects of a non-uniform thermal contact resistance and a potential misalignment of the monoblock fibers. And while the difference between the experimental and computational results was not resolved by a non-uniform thermal contact resistance, the computational results provided insight into the potential performance of a W7-X monoblock unit. Circumferential temperature distributions highlighted the expected boiling regions ofmore »« less

Authors:

Clark, Emily ^[1];

^[2]; Boscary, Jean ^[3]; Greuner, Henri ^[3]; Ekici, Kivanc ^[1]

Univ. of Tennessee, Knoxville, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Max Planck Inst. for Plasma Physics, Garching (Germany)

Publication Date:: Fri Jul 28 00:00:00 EDT 2017

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

OSTI Identifier:: 1394229

Alternate Identifier(s):: OSTI ID: 1549695

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Fusion Engineering and Design

Additional Journal Information:: Journal Volume: 121; Journal Issue: C; Journal ID: ISSN 0920-3796

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; plasma facing components; monoblock; CFC; high heat flux

Citation Formats


                    Clark, Emily, Lumsdaine, Arnold, Boscary, Jean, Greuner, Henri, and Ekici, Kivanc. Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element.  United States: N. p., 2017. 
Web.  doi:10.1016/j.fusengdes.2017.07.014.

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                    Clark, Emily, Lumsdaine, Arnold, Boscary, Jean, Greuner, Henri, & Ekici, Kivanc. Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element.  United States.  https://doi.org/10.1016/j.fusengdes.2017.07.014

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                    Clark, Emily, Lumsdaine, Arnold, Boscary, Jean, Greuner, Henri, and Ekici, Kivanc. Fri .  
"Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element".  United States.  https://doi.org/10.1016/j.fusengdes.2017.07.014.  https://www.osti.gov/servlets/purl/1394229.

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@article{osti_1394229,

  title        = {Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element},

  author       = {Clark, Emily and Lumsdaine, Arnold and Boscary, Jean and Greuner, Henri and Ekici, Kivanc},

  abstractNote = {The long-pulse operation of the Wendelstein 7-X (W7-X) stellarator experiment is scheduled to begin in 2020. This operational phase will be equipped with water-cooled plasma facing components to allow for longer pulse durations. Certain simulated plasma scenarios have been shown to produce heat fluxes that surpass the technological limits on the edges of the divertor target elements during steady-state operation. In order to reduce the heat load on the target elements, the addition of a “scraper element” (SE) is under investigation. The SE is composed of 24 water-cooled carbon fiber reinforced carbon composite monoblock units. Multiple full-scale prototypes have been tested in the GLADIS high heat flux test facility. Previous computational studies revealed discrepancies between the simulations and experimental measurements. In this work, single-phase thermal-hydraulics modeling was performed in ANSYS CFX to identify potential causes for such discrepancies. Possible explanations investigated were the effects of a non-uniform thermal contact resistance and a potential misalignment of the monoblock fibers. And while the difference between the experimental and computational results was not resolved by a non-uniform thermal contact resistance, the computational results provided insight into the potential performance of a W7-X monoblock unit. Circumferential temperature distributions highlighted the expected boiling regions of such a unit. Finally, simulations revealed that modest angles of fiber misalignment in the monoblocks result in asymmetries at the unit edges and provide temperature differences similar to the experimental results.},

  doi          = {10.1016/j.fusengdes.2017.07.014},

  journal      = {Fusion Engineering and Design},

  number       = C,

  volume       = 121,

  place        = {United States},

  year         = {Fri Jul 28 00:00:00 EDT 2017},

  month        = {Fri Jul 28 00:00:00 EDT 2017}

}

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