Thermohydraulic and mechanical design assessment of tube-panel first wall for tokamak fusion power reactor
Journal Article
·
· J. Fusion Energy; (United States)
A first wall structural concept cooled by high temperature and pressurized water has been proposed for the Tokamak Fusion Power Reactor (SPTR-P). Among a number of candidate design concepts, a tube-panel structure was selected for the first wall design. Stainless steel serves as the first wall structural material. The first wall is separated from the blanket wall and has a circular cross-section coolant channel since this shape is the most desirable for resisting the mechanical load due to the pressurized cooling water. Feasibility of the thermohydraulic and mechanical design has been established by analyses under steady-state operating conditions. The effect of the heat load during plasma disruptions on the thermomechanical characteristics of the first wall has been clarified. The mechanical strength of the first wall of power reactor is inadequate to withstand the thermal load expected during plasma disruption in an experimental reactor.
- Research Organization:
- Naka Fusion Research Establishment, JAERI
- OSTI ID:
- 6722136
- Journal Information:
- J. Fusion Energy; (United States), Journal Name: J. Fusion Energy; (United States) Vol. 5:3; ISSN JFEND
- 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
700204 -- Fusion Power Plant Technology-- Cooling Systems
ALLOYS
BREEDING BLANKETS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
DESIGN
ENERGY SYSTEMS
ENERGY TRANSFER
EXPANSION
FIRST WALL
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MECHANICS
PHYSICAL PROPERTIES
PLASMA DISRUPTION
REACTOR COMPONENTS
SHIELDS
SPECIFIC HEAT
STAINLESS STEELS
STEELS
STRESS ANALYSIS
TEMPERATURE EFFECTS
THERMAL CONDUCTIVITY
THERMAL EXPANSION
THERMAL SHIELDS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700204 -- Fusion Power Plant Technology-- Cooling Systems
ALLOYS
BREEDING BLANKETS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
DESIGN
ENERGY SYSTEMS
ENERGY TRANSFER
EXPANSION
FIRST WALL
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MECHANICS
PHYSICAL PROPERTIES
PLASMA DISRUPTION
REACTOR COMPONENTS
SHIELDS
SPECIFIC HEAT
STAINLESS STEELS
STEELS
STRESS ANALYSIS
TEMPERATURE EFFECTS
THERMAL CONDUCTIVITY
THERMAL EXPANSION
THERMAL SHIELDS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS