THERMAL HYDRAULIC ANALYSIS OF FIRE DIVERTOR

Conference · Sun Oct 01 04:00:00 EDT 2000

OSTI ID:808789

bAXI, C B ^[1]; ULRICKSON, M A; DRIMEYER, D E; HEITZENROEDER, P

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1. General Atomics

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.

• Research Organization: GENERAL ATOMICS (US)
• Sponsoring Organization: (US)
• DOE Contract Number: AC03-98ER54411
• OSTI ID: 808789
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CRITICAL HEAT FLUX
DIVERTORS
ELECTRIC CURRENTS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
IGNITION
PRESSURE DROP
THERMONUCLEAR REACTORS
TUNGSTEN