TY - GEN
T1 - Structural analysis of high-field-side RF antennas during a disruption on the Advanced Divertor eXperiment (ADX)
AU - Doody, J.
AU - LaBombard, B.
AU - Leccacorvi, R.
AU - Shiraiwa, S.
AU - Vieira, R.
AU - Wallace, G. M.
AU - Wukitch, S. J.
AU - Irby, J. H.
N1 - Publisher Copyright:
© 2015 IEEE.
PY - 2016/5/31
Y1 - 2016/5/31
N2 - The Advanced Divertor and RF tokamak eXperiment (ADX) is a compact, high-field device proposed by the MIT Plasma Science and Fusion Center and collaborators [1], which will address critical gaps in world fusion research on the pathway to fusion energy. In addition to developing and testing new divertor concepts at reactor level magnetic field strengths and power densities, ADX will test new antenna concepts for Lower Hybrid Current Drive (LHCD) and Ion Cyclotron Range of Frequency (ICRF) heating systems. In particular, ADX will be purpose-built to allow antennas to be positioned on the high magnetic field side of the torus, i.e., on the inner wall. With antennas placed at this location, plasma-wall interactions are greatly reduced and favorable RF wave physics projects to dramatic improvements in current drive efficiency and current profile control as well as very effective scenarios for RF heating and flow drive [2][3][4]. Initial designs for a high field side LHCD and ICRF antennas have been completed and are analyzed to determine the loads induced during a full-current plasma disruption. While locating antennas at the inner wall is beneficial from an RF standpoint, it exposes them to a higher toroidal field which, when combined with the eddy currents caused by a disrupting plasma, will lead to higher loads. Using COMSOL Multiphysics [5], a model of the ADX vessel and coils is created to predict the magnetic fields, eddy currents and loads acting on the antennas during a disruption. Structural models are then run to predict the stresses and to provide guidance for design improvement, such as determining where structural reinforcements may be necessary.
AB - The Advanced Divertor and RF tokamak eXperiment (ADX) is a compact, high-field device proposed by the MIT Plasma Science and Fusion Center and collaborators [1], which will address critical gaps in world fusion research on the pathway to fusion energy. In addition to developing and testing new divertor concepts at reactor level magnetic field strengths and power densities, ADX will test new antenna concepts for Lower Hybrid Current Drive (LHCD) and Ion Cyclotron Range of Frequency (ICRF) heating systems. In particular, ADX will be purpose-built to allow antennas to be positioned on the high magnetic field side of the torus, i.e., on the inner wall. With antennas placed at this location, plasma-wall interactions are greatly reduced and favorable RF wave physics projects to dramatic improvements in current drive efficiency and current profile control as well as very effective scenarios for RF heating and flow drive [2][3][4]. Initial designs for a high field side LHCD and ICRF antennas have been completed and are analyzed to determine the loads induced during a full-current plasma disruption. While locating antennas at the inner wall is beneficial from an RF standpoint, it exposes them to a higher toroidal field which, when combined with the eddy currents caused by a disrupting plasma, will lead to higher loads. Using COMSOL Multiphysics [5], a model of the ADX vessel and coils is created to predict the magnetic fields, eddy currents and loads acting on the antennas during a disruption. Structural models are then run to predict the stresses and to provide guidance for design improvement, such as determining where structural reinforcements may be necessary.
KW - ADX
KW - High field side launch
KW - ICRF
KW - Lower Hybrid
UR - https://www.scopus.com/pages/publications/84978900596
UR - https://www.scopus.com/pages/publications/84978900596#tab=citedBy
U2 - 10.1109/SOFE.2015.7482318
DO - 10.1109/SOFE.2015.7482318
M3 - Conference contribution
AN - SCOPUS:84978900596
T3 - Proceedings - Symposium on Fusion Engineering
BT - 2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015
PB - Institute of Electrical and Electronics Engineers Inc.
T2 - 26th IEEE Symposium on Fusion Engineering, SOFE 2015
Y2 - 31 May 2015 through 4 June 2015
ER -