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Title: The integrated-blanket-coil concept applied to the poloidal field and blanket systems of a tokamak reactor

Journal Article · · Fusion Technol.; (United States)
OSTI ID:5869166

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