The integrated-blanket-coil concept applied to the poloidal field and blanket systems of a tokamak reactor
A novel concept is proposed for combining the blanket and coil functions of a fusion reactor into a single component. This concept, designated the ''integrated-blanket-coil'' (IBC) concept, is applied to the poloidal field and blanket systems of a tokamak reactor. An examination of resistive power losses in the IBC suggests that these losses can be limited to 10% of the fusion thermal power. By assuming a sandwich construction for the IBC walls, magnetohydrodynamic (MHD)-induced pressure drops and associated pressure stresses are shown to be modest and well below design limits. For the stainless steel reference case examined, the MHD-induced pressure drop was estimated to be about 1/3 MPa and the associated primary membrane stress was estimated to be about 47 MPa. The preliminary analyses indicate that the IBC concept offers promise as a means for making fusion reactors more compact by combining blanket and coil functions in a single component.
- Research Organization:
- Rensselaer Polytechnic Institute, Department of Nuclear Engineering, Troy, NY
- OSTI ID:
- 5869166
- Journal Information:
- Fusion Technol.; (United States), Vol. 7:1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
CONFIGURATION
MAGNET COILS
TOKAMAK TYPE REACTORS
DESIGN
EFFICIENCY
FEASIBILITY STUDIES
MAGNETOHYDRODYNAMICS
POLOIDAL FIELD DIVERTORS
POWER LOSSES
PRESSURE DROP
PRESSURE EFFECTS
STAINLESS STEELS
STRESS ANALYSIS
ALLOYS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
DIVERTORS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
ENERGY LOSSES
EQUIPMENT
FLUID MECHANICS
HYDRODYNAMICS
IRON ALLOYS
IRON BASE ALLOYS
LOSSES
MECHANICS
REACTOR COMPONENTS
STEELS
THERMONUCLEAR REACTORS
700202* - Fusion Power Plant Technology- Magnet Coils & Fields
700201 - Fusion Power Plant Technology- Blanket Engineering