Design considerations for ITER (International Thermonuclear Experimental Reactor) plasma facing components
Technical Report
·
OSTI ID:5755371
The International Thermonuclear Experimental Reactor (ITER) is a joint design and R D project involving the USA, the Soviet Union, Japan and the European Community. These international partners are working together on the design of a fusion tokamak reactor that will operate in the D-T ignition regime. This report compiles the contributions to ITER made by Sandia National Laboratories in the area of design and R D for plasma facing components, such as the first wall and divertor. The following topics are discussed: divertor fabrication issues, divertor thermal-hydraulic analysis, separatrix sweeping effects, divertor tile 2-D stress analysis, electromechanical disruption effects, runaway electron and intense energy deposition analyses, lifetime analysis and tritium retention in plasma facing materials. Material properties for pyrolytic graphite and beryllium are presented. Use of pyrolytic graphite as the plasma facing material allows for operation with thicker graphite armor at the design heat flux level of 10 MW/m/sup 2/. The design of a divertor coated with plasma sprayed beryllium is presented as an attractive alternative to pyrolytic graphite armor tiles. Finally, the Sandia research and development plan for ITER is discussed. 82 figs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5755371
- Report Number(s):
- SAND-89-0901; ON: DE89015200
- Country of Publication:
- United States
- Language:
- English
Similar Records
Beryllium, an alternative material for plasma-facing components
ITER divertor research and development activities
Beryllium processing technology review for applications in plasma-facing components
Journal Article
·
Mon Jul 01 00:00:00 EDT 1991
· Fusion Technology; (United States)
·
OSTI ID:5920131
ITER divertor research and development activities
Journal Article
·
Mon Oct 31 23:00:00 EST 1994
· Fusion Technology
·
OSTI ID:41463
Beryllium processing technology review for applications in plasma-facing components
Technical Report
·
Thu Jul 01 00:00:00 EDT 1993
·
OSTI ID:10176907
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALINE EARTH METALS
BENCHMARKS
BERYLLIUM
CARBON
CLOSED PLASMA DEVICES
DESIGN
DIVERTORS
ELEMENTAL MINERALS
ELEMENTS
ENERGY TRANSFER
FIRST WALL
FLUID MECHANICS
GRAPHITE
HEAT TRANSFER
HYDRAULICS
ITER TOKAMAK
MECHANICS
METALS
MINERALS
NONMETALS
PLASMA DISRUPTION
STRESS ANALYSIS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALINE EARTH METALS
BENCHMARKS
BERYLLIUM
CARBON
CLOSED PLASMA DEVICES
DESIGN
DIVERTORS
ELEMENTAL MINERALS
ELEMENTS
ENERGY TRANSFER
FIRST WALL
FLUID MECHANICS
GRAPHITE
HEAT TRANSFER
HYDRAULICS
ITER TOKAMAK
MECHANICS
METALS
MINERALS
NONMETALS
PLASMA DISRUPTION
STRESS ANALYSIS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES