Plasma engineering analysis of Tennessee Tokamak

Conference · Sat Jan 01 04:00:00 EST 1983

OSTI ID:5399019

Yokoyama, K E; Lacatski, J T; Miller, J B; Bryan, W E; King, P W; Santoro, R T; Shannon, T E; Uckan, N A

This paper summarizes the results of the plasma engineering and systems analysis studies for the Tennessee Tokamak (TENTOK) fusion power reactor. TENTOK is a 3000-MW(t) central station power plant that uses dueterium-tritium fuel in a D-shaped tokamak plasma configuration with a double-null poloidal divertor. Detailed analyses are performed in the areas of (1) transport simulation using the 1-1/2-D WHIST transport code, (2) equilibrium/poloidal field coil systems, (3) neutral beam and radiofrequency (rf) heating, and (4) pellet fueling. In addition, impurity control sytems, diagnostics and controls, and possible microwave plasma preheating and steady-state current drive options are also considered. Some of the major features of TENTOK include rf heating in the ion cyclotron range of frequencies, superconducting equilibrium field coils outside the superconducting toroidal field coils, a double-null poloidal divertor for impurity control and alpha ash removal, and rf-assisted plasma preheating and current startup.

• Research Organization: Tennessee Univ., Knoxville (USA). Dept. of Nuclear Engineering; Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5399019
• Report Number(s): CONF-831203-55-Draft; ON: DE84004692
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
CLOSED PLASMA DEVICES
DIVERTORS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
ELEMENTS
ENGINEERING
EQUIPMENT
FLUIDS
GASES
HELIUM
MAGNET COILS
NONMETALS
POLOIDAL DIVERTORS
RARE GASES
REACTOR FUELING
SPECIFICATIONS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TRANSPORT THEORY