TY - GEN
T1 - Plasma shape control calculations for BPX divertor design
AU - Strickler, D. J.
AU - Neilson, G. H.
AU - Jardin, S. C.
AU - Pomphrey, N.
N1 - Publisher Copyright:
© 1991 IEEE.
PY - 1991
Y1 - 1991
N2 - The Burning Plasma Experiment (BPX) divertor is to be capable of withstanding heat loads corresponding to ignited operation and 500 MW of fusion power for a current rise time and flattop lasting several seconds. The poloidal field (PF), diagnostic, and feedback equilibrium control systems must provide precise X-point position control in order to sweep the separatrices across the divertor target surface and optimally distribute the heat loads. A control matrix MHD equilibrium code, BEQ, and the Tokamak Simulation Code (TSC) are used to compute preprogrammed double-null (DN) divertor sweep trajectories that maximize sweep distance while simultaneously satisfying a set of strict constraints: minimum lengths of the field lines between the X- point and strike points, minimum spacing between the inboard plasma edge and the limiter, maximum spacing between the outboard plasma edge and the ICRF antennas, minimum safety factor, and linked poloidal flux. A sequence of DN diverted equilibria and a consistent TSC fiducial discharge simulation are used in evaluating the performance of the BPX divertor shape and possible modifications.
AB - The Burning Plasma Experiment (BPX) divertor is to be capable of withstanding heat loads corresponding to ignited operation and 500 MW of fusion power for a current rise time and flattop lasting several seconds. The poloidal field (PF), diagnostic, and feedback equilibrium control systems must provide precise X-point position control in order to sweep the separatrices across the divertor target surface and optimally distribute the heat loads. A control matrix MHD equilibrium code, BEQ, and the Tokamak Simulation Code (TSC) are used to compute preprogrammed double-null (DN) divertor sweep trajectories that maximize sweep distance while simultaneously satisfying a set of strict constraints: minimum lengths of the field lines between the X- point and strike points, minimum spacing between the inboard plasma edge and the limiter, maximum spacing between the outboard plasma edge and the ICRF antennas, minimum safety factor, and linked poloidal flux. A sequence of DN diverted equilibria and a consistent TSC fiducial discharge simulation are used in evaluating the performance of the BPX divertor shape and possible modifications.
UR - https://www.scopus.com/pages/publications/85067678226
UR - https://www.scopus.com/inward/citedby.url?scp=85067678226&partnerID=8YFLogxK
U2 - 10.1109/FUSION.1991.218694
DO - 10.1109/FUSION.1991.218694
M3 - Conference contribution
AN - SCOPUS:85067678226
T3 - Proceedings - Symposium on Fusion Engineering
SP - 937
EP - 939
BT - Proceedings - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991
PB - Institute of Electrical and Electronics Engineers Inc.
T2 - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991
Y2 - 30 September 1991 through 3 October 1991
ER -