Plasma simulation and surface effects in a high-field tokamak ignition experiment
Conference
·
· Fusion Technol.; (United States)
OSTI ID:6276471
Plasma loading of the wall and limiter surfaces will play an important part in ignited tokamak experiments. Fusion plasmas will be characterized by high edge temperatures and large radially outward particle and energy fluxes. Many aspects of plasma-surface interactions presently seen in tokamak experiments will change and altogether new phenomena may appear. In this paper the authors identify possible plasma-surface interactions in a tokamak ignition experiment which can significantly affect its operation. The proposed ignition experiment, IGNITEX, is considered. The IGNITEX experiment uses a single-turn coil to produce a 20 Tesla toroidal field in a compact tokamak. A deuterium-tritium plasma will be gas fueled and ohmically heated to ignition. To obtain detailed edge plasma profiles and fluxes, a 1-D transport code is utilized. Ion and charge-exchange neutral sputtering processes at an all carbon surface system are included. A detailed description of the radial particle and energy flux calculations is given.
- Research Organization:
- UT-Center for Fusion Engineering, Austin, TX (US)
- OSTI ID:
- 6276471
- Report Number(s):
- CONF-881031-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 15:2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700208* -- Fusion Power Plant Technology-- Inertial Confinement Technology
CHARGED-PARTICLE TRANSPORT
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
COMPUTER CODES
D-T REACTORS
DATA
EXPERIMENTAL DATA
FIRST WALL
HEAT FLUX
HEATING
HIGH TEMPERATURE
I CODES
INFORMATION
INTERACTIONS
LIMITERS
NUMERICAL DATA
ONE-DIMENSIONAL CALCULATIONS
PLASMA
PLASMA HEATING
PLASMA SIMULATION
RADIATION TRANSPORT
SIMULATION
STEADY-STATE D-T REACTORS
STEADY-STATE FUSION REACTORS
SURFACES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700208* -- Fusion Power Plant Technology-- Inertial Confinement Technology
CHARGED-PARTICLE TRANSPORT
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
COMPUTER CODES
D-T REACTORS
DATA
EXPERIMENTAL DATA
FIRST WALL
HEAT FLUX
HEATING
HIGH TEMPERATURE
I CODES
INFORMATION
INTERACTIONS
LIMITERS
NUMERICAL DATA
ONE-DIMENSIONAL CALCULATIONS
PLASMA
PLASMA HEATING
PLASMA SIMULATION
RADIATION TRANSPORT
SIMULATION
STEADY-STATE D-T REACTORS
STEADY-STATE FUSION REACTORS
SURFACES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS