Divertor design for the Tokamak Physics Experiment

Conference · Sun May 01 04:00:00 EDT 1994

OSTI ID:10196606

Hill, D N ^[1]; Braams, B ^[2]; Brooks, J N ^[3]

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1. Lawrence Livermore National Lab., CA (United States)
2. New York Univ., NY (United States). Courant Inst.
3. Argonne National Lab., IL (United States)

In this paper we discuss the present divertor design for the planned TPX tokamak, which will explore the physics and technology of steady-state (1000s pulses) heat and particle removal in high confinement (2--4{times} L-mode), high beta ({beta}{sub N} {ge} 3) divertor plasmas sustained by non-inductive current drive. The TPX device will operate in the double-null divertor configuration, with actively cooled graphite targets forming a deep (0.5 m) slot at the outer strike point. The peak heat flux on, the highly tilted (74{degrees} from normal) re-entrant (to recycle ions back toward the separatrix) will be in the range of 4--6 MW/m{sup 2} with 18 MW of neutral beams and RF heating power. The combination of active pumping and gas puffing (deuterium plus impurities), along with higher heating power (45 MW maximum) will allow testing of radiative divertor concepts at ITER-like power densities.

• Research Organization: Lawrence Livermore National Lab., CA (United States); Princeton Univ., NJ (United States). Plasma Physics Lab.
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-48; AC02-76CH03073
• OSTI ID: 10196606
• Report Number(s): UCRL-JC--115492; CONF-940580--22; ON: DE95003653
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700420
DESIGN
DIVERTORS
NON-INDUCTIVE CURRENT DRIVE
PLASMA HEATING
PLASMA-FACING COMPONENTS
TPX DEVICE