Impact of an 'inter linked' central solenoid configuration on the size of tokamak DEMO

Makoto Nakamura; Kenji Tobita; Hiroyasu Utoh; Yoshiteru Sakamoto

doi:10.1016/j.fusengdes.2013.01.097

Impact of an 'inter linked' central solenoid configuration on the size of tokamak DEMO

Makoto Nakamura, Kenji Tobita, Hiroyasu Utoh, Yoshiteru Sakamoto

Research output: Contribution to journal › Article › peer-review

2 Citations (Scopus)

Abstract

Operation points of a tokamak fusion DEMO in the conventional (C-) and "inter-linked" (IL-) CS configurations are analyzed. A specific feature of the systems analysis presented here is that it is consistent with superconducting toroidal field coil (TFC) system analysis. It is shown that in order to achieve the fusion power of the order of gigawatt with the inductive plasma current ramp-up, the large reactor size is needed for the C-CS configuration. Use of the IL-CS configuration enables to reduce the plasma major radius and, in turn, the reactor size compatible with both the large fusion power and inductive plasma current ramp-up.

Original language	English
Pages (from-to)	1146-1149
Number of pages	4
Journal	Fusion Engineering and Design
Volume	88
Issue number	6-8
DOIs	https://doi.org/10.1016/j.fusengdes.2013.01.097
Publication status	Published - 2013 Mar 15
Externally published	Yes

Keywords

Fusion reactor design
Inter-linked central solenoid
Magnetic flux swing
Plasma current ramp-up
Systems analysis

ASJC Scopus subject areas

Civil and Structural Engineering
Nuclear Energy and Engineering
Materials Science(all)
Mechanical Engineering

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AU - Nakamura, Makoto

AU - Tobita, Kenji

AU - Utoh, Hiroyasu

AU - Sakamoto, Yoshiteru

PY - 2013/3/15

Y1 - 2013/3/15

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AB - Operation points of a tokamak fusion DEMO in the conventional (C-) and "inter-linked" (IL-) CS configurations are analyzed. A specific feature of the systems analysis presented here is that it is consistent with superconducting toroidal field coil (TFC) system analysis. It is shown that in order to achieve the fusion power of the order of gigawatt with the inductive plasma current ramp-up, the large reactor size is needed for the C-CS configuration. Use of the IL-CS configuration enables to reduce the plasma major radius and, in turn, the reactor size compatible with both the large fusion power and inductive plasma current ramp-up.

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