Abstract
A study was carried out to assess the feasibility of the DIOSCUR tokamak (divertor optimization and steady current) which could sustain a plasma discharge in steady state and which would have reactor parameters such as to contemporaneously obtain Q>>1 with a D-T gas mixture. Critical design elements include the use of forced flow superconducting coils and full use of remote handling. The design parameters were chosen to be between those of the JET and ITER tokamaks, with the important exception of the toroidal field value, i.e., 7 T. In H-mode, the value of the average temperature is expected to be above 10 keV at plasma densities of 10/sup 20/ per cubic meter, with a total additional heating power of 50 MW. A high current configuration can be set-up with plasma currents up to 18 MA, and a high aspect ratio configuration can have values of the aspect ratio of 5.2 in order to take full advantage of the high beta poloidal bootstrap current contribution. The 16 toroidal field coils are based on Nb/sub 3/Sn conductors developed for NET/ITER. The shape of the TF coils is nearly momentum bending free. The plasma current drive is largely based on LHCD and negative
More>>
Citation Formats
Alladio, F, Barbato, E, Bartiromo, R, Cardinali, A, De Marco, F, Ferro, C, Gasparotto, M, Lovisetto, L, Mancuso, A, and Micozzi, P.
DIOSCUR-divertor optimization and steady current: Study of a Tokamak aimed at steady state operation with reactor relevant plasma parameters.
Italy: N. p.,
1992.
Web.
Alladio, F, Barbato, E, Bartiromo, R, Cardinali, A, De Marco, F, Ferro, C, Gasparotto, M, Lovisetto, L, Mancuso, A, & Micozzi, P.
DIOSCUR-divertor optimization and steady current: Study of a Tokamak aimed at steady state operation with reactor relevant plasma parameters.
Italy.
Alladio, F, Barbato, E, Bartiromo, R, Cardinali, A, De Marco, F, Ferro, C, Gasparotto, M, Lovisetto, L, Mancuso, A, and Micozzi, P.
1992.
"DIOSCUR-divertor optimization and steady current: Study of a Tokamak aimed at steady state operation with reactor relevant plasma parameters."
Italy.
@misc{etde_10134945,
title = {DIOSCUR-divertor optimization and steady current: Study of a Tokamak aimed at steady state operation with reactor relevant plasma parameters}
author = {Alladio, F, Barbato, E, Bartiromo, R, Cardinali, A, De Marco, F, Ferro, C, Gasparotto, M, Lovisetto, L, Mancuso, A, and Micozzi, P}
abstractNote = {A study was carried out to assess the feasibility of the DIOSCUR tokamak (divertor optimization and steady current) which could sustain a plasma discharge in steady state and which would have reactor parameters such as to contemporaneously obtain Q>>1 with a D-T gas mixture. Critical design elements include the use of forced flow superconducting coils and full use of remote handling. The design parameters were chosen to be between those of the JET and ITER tokamaks, with the important exception of the toroidal field value, i.e., 7 T. In H-mode, the value of the average temperature is expected to be above 10 keV at plasma densities of 10/sup 20/ per cubic meter, with a total additional heating power of 50 MW. A high current configuration can be set-up with plasma currents up to 18 MA, and a high aspect ratio configuration can have values of the aspect ratio of 5.2 in order to take full advantage of the high beta poloidal bootstrap current contribution. The 16 toroidal field coils are based on Nb/sub 3/Sn conductors developed for NET/ITER. The shape of the TF coils is nearly momentum bending free. The plasma current drive is largely based on LHCD and negative ions with a total power of 50 MW. ICRF heating and Fast Wave CD were also considered. The poloidal divertor is a double null with radial and verticle sweeping. It is equipped with cryopumps, ergodization coils and a full set of diagnostics.}
place = {Italy}
year = {1992}
month = {Dec}
}
title = {DIOSCUR-divertor optimization and steady current: Study of a Tokamak aimed at steady state operation with reactor relevant plasma parameters}
author = {Alladio, F, Barbato, E, Bartiromo, R, Cardinali, A, De Marco, F, Ferro, C, Gasparotto, M, Lovisetto, L, Mancuso, A, and Micozzi, P}
abstractNote = {A study was carried out to assess the feasibility of the DIOSCUR tokamak (divertor optimization and steady current) which could sustain a plasma discharge in steady state and which would have reactor parameters such as to contemporaneously obtain Q>>1 with a D-T gas mixture. Critical design elements include the use of forced flow superconducting coils and full use of remote handling. The design parameters were chosen to be between those of the JET and ITER tokamaks, with the important exception of the toroidal field value, i.e., 7 T. In H-mode, the value of the average temperature is expected to be above 10 keV at plasma densities of 10/sup 20/ per cubic meter, with a total additional heating power of 50 MW. A high current configuration can be set-up with plasma currents up to 18 MA, and a high aspect ratio configuration can have values of the aspect ratio of 5.2 in order to take full advantage of the high beta poloidal bootstrap current contribution. The 16 toroidal field coils are based on Nb/sub 3/Sn conductors developed for NET/ITER. The shape of the TF coils is nearly momentum bending free. The plasma current drive is largely based on LHCD and negative ions with a total power of 50 MW. ICRF heating and Fast Wave CD were also considered. The poloidal divertor is a double null with radial and verticle sweeping. It is equipped with cryopumps, ergodization coils and a full set of diagnostics.}
place = {Italy}
year = {1992}
month = {Dec}
}