Thermo-structural and thermal-hydraulic aspects of the STARFIRE/DEMO tritium breeding blanket
The STARFIRE/DEMO Project has performed a conceptual design study of the demonstration fusion power reactor to follow the FED/INTOR class of experimental tokamaks. This paper discusses thermo-structural and thermal-hydraulic aspects of two fundamentally different first wall and tritium breeding blanket concepts for STARFIRE/DEMO. The first concept uses solid lithium oxide (Li/sub 2/O) as the tritium breeder in a modular blanket. The first wall is a flat corrugated panel. Both first wall and blanket are constructed of titanium-modified austenitic stainless steel and are cooled with pressurized high-temperature water. The second concept features a liquid metal, 17Li-83Pb, as tritium breeder and coolant. The blanket module's two semi-cylindrical front walls form the first wall, the back faces of which are cooled by flowing liquid metal. Ferritic steel and vanadium alloy are the candidate structural materials.
- Research Organization:
- Argonne National Lab., IL (USA); McDonnell Douglas Astronautics Co., St. Louis, MO (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6028845
- Report Number(s):
- CONF-830805-30; ON: DE83010722
- Country of Publication:
- United States
- Language:
- English
Similar Records
Assessments of tritium-breeding requirements and breeding potential for the STARFIRE/DEMO design
Self-cooled liquid-metal blanket concept
Related Subjects
700204* -- Fusion Power Plant Technology-- Cooling Systems
ALLOYS
COOLANTS
COOLING SYSTEMS
ENERGY SYSTEMS
FLUID MECHANICS
HYDRAULICS
LEAD ALLOYS
LITHIUM ALLOYS
MECHANICS
PHYSICAL PROPERTIES
STARFIRE TOKAMAK
STRESS ANALYSIS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
VELOCITY