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Title: 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}
}

Technical Report:
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