Integrated-blanket-coil (IBC) concept applied to the poloidal field and blanket systems of a tokamak reactor
Abstract
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.
- Authors:
- Publication Date:
- Research Org.:
- Rensselaer Polytechnic Inst., Troy, NY (USA). Dept. of Nuclear Engineering
- OSTI Identifier:
- 6461997
- Report Number(s):
- DOE/ER/53163-1
ON: DE85000437
- DOE Contract Number:
- AC02-83ER53163
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 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
Citation Formats
Steiner, D, Block, R C, and Malaviya, B K. Integrated-blanket-coil (IBC) concept applied to the poloidal field and blanket systems of a tokamak reactor. United States: N. p., 1983.
Web.
Steiner, D, Block, R C, & Malaviya, B K. Integrated-blanket-coil (IBC) concept applied to the poloidal field and blanket systems of a tokamak reactor. United States.
Steiner, D, Block, R C, and Malaviya, B K. 1983.
"Integrated-blanket-coil (IBC) concept applied to the poloidal field and blanket systems of a tokamak reactor". United States.
@article{osti_6461997,
title = {Integrated-blanket-coil (IBC) concept applied to the poloidal field and blanket systems of a tokamak reactor},
author = {Steiner, D and Block, R C and Malaviya, B K},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/6461997},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Jan 01 00:00:00 EST 1983},
month = {Sat Jan 01 00:00:00 EST 1983}
}