Integrated-blanket-coil (IBC) concept applied to the poloidal field and blanket systems of a tokamak reactor

Technical Report · Sat Jan 01 00:00:00 EST 1983

OSTI ID:6461997

Steiner, D; Block, R C; Malaviya, B K

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 less than or equal to 10% of the fusion thermal power. By assuming a sandwich construction for the IBC walls, 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 in this paper, the MHD-induced pressure drop was estimated to be approx. 1/3 MPa and the associated primary membrane stress was estimated to be approx. 47 MPa. The preliminary analyses presented in this paper indicate that the IBC concept offers promise as a means for making fusion reactors more compact by combining blanket and coils functions in a single component.

• Research Organization: Rensselaer Polytechnic Inst., Troy, NY (USA). Dept. of Nuclear Engineering
• DOE Contract Number: AC02-83ER53163
• OSTI ID: 6461997
• Report Number(s): DOE/ER/53163-1; ON: DE85000437
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
DESIGN
MAGNET COILS
TOKAMAK TYPE REACTORS
ENERGY LOSSES
RADIATIONS
STAINLESS STEELS
ALLOYS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
IRON ALLOYS
IRON BASE ALLOYS
LOSSES
REACTOR COMPONENTS
STEELS
THERMONUCLEAR REACTORS
700200* - Fusion Energy- Fusion Power Plant Technology