TY - JOUR
T1 - Impact of an 'inter linked' central solenoid configuration on the size of tokamak DEMO
AU - Nakamura, Makoto
AU - Tobita, Kenji
AU - Utoh, Hiroyasu
AU - Sakamoto, Yoshiteru
PY - 2013
Y1 - 2013
N2 - 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.
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.
KW - Fusion reactor design
KW - Inter-linked central solenoid
KW - Magnetic flux swing
KW - Plasma current ramp-up
KW - Systems analysis
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U2 - 10.1016/j.fusengdes.2013.01.097
DO - 10.1016/j.fusengdes.2013.01.097
M3 - Article
AN - SCOPUS:84885298137
SN - 0920-3796
VL - 88
SP - 1146
EP - 1149
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
IS - 6-8
ER -