THERMAL HYDRAULIC ANALYSIS OF FIRE DIVERTOR

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The Fusion Ignition Research Experiment (FIRE) is being designed as a next step in the US magnetic fusion program. The FIRE tokamak has a major radius of 2 m, a minor radius of 0.525 m, and liquid nitrogen cooled copper coils. The aim is to produce a pulse length of 20 s with a plasma current of 6.6 MA and with alpha dominated heating. The outer divertor and baffle of FIRE are water cooled. The worst thermal condition for the outer divertor and baffle is the baseline D-T operating mode (10 T, 6.6 MA, 20 s) with a plasma exhaust ... continued below

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5 pages

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bAXI, C.B.; ULRICKSON, M.A.; DRIMEYER, D.E. & HEITZENROEDER, P. October 1, 2000.

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Description

The Fusion Ignition Research Experiment (FIRE) is being designed as a next step in the US magnetic fusion program. The FIRE tokamak has a major radius of 2 m, a minor radius of 0.525 m, and liquid nitrogen cooled copper coils. The aim is to produce a pulse length of 20 s with a plasma current of 6.6 MA and with alpha dominated heating. The outer divertor and baffle of FIRE are water cooled. The worst thermal condition for the outer divertor and baffle is the baseline D-T operating mode (10 T, 6.6 MA, 20 s) with a plasma exhaust power of 67 MW and a peak heat flux of 20 MW/m{sup 2}. A swirl tape (ST) heat transfer enhancement method is used in the outer divertor cooling channels to increase the heat transfer coefficient and the critical heat flux (CHF). The plasma-facing surface consists of tungsten brush. The finite element (FE) analysis shows that for an inlet water temperature of 30 C, inlet pressure of 1.5 MPa and a flow velocity of 10 m/s, the incident critical heat flux is greater than 30 MW/m{sup 2}. The peak copper temperature is 490 C, peak tungsten temperature is 1560 C, and the pressure drop is less than 0.5 MPa. All these results fulfill the design requirements.

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5 pages

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Oakland Operations Office, Oakland, CA (US); INIS

Source

  • 14th Topical Meeting on Technology of Fusion Energy, Park City, UT (US), 10/15/2000--10/19/2000; Other Information: This is a preprint of a paper to be presented at the 14th Topical Meeting on Technology of Fusion Energy, October 15-19, 2000, in Park City, Utah, and to be published in the Fusion Technology.

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  • Report No.: NONE
  • Grant Number: AC03-98ER54411
  • Office of Scientific & Technical Information Report Number: 808789
  • Archival Resource Key: ark:/67531/metadc737071

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  • October 1, 2000

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  • Oct. 18, 2015, 6:40 p.m.

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  • Jan. 4, 2017, 2:08 p.m.

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bAXI, C.B.; ULRICKSON, M.A.; DRIMEYER, D.E. & HEITZENROEDER, P. THERMAL HYDRAULIC ANALYSIS OF FIRE DIVERTOR, article, October 1, 2000; United States. (digital.library.unt.edu/ark:/67531/metadc737071/: accessed August 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.