Vertical displacement event（VDE） is a big challenge to the existing tokamak equipment and that being designed. As a Chinese next-step tokamak, the Chinese Fusion Engineering Test Reactor（CFETR） has to pay attentio...Vertical displacement event（VDE） is a big challenge to the existing tokamak equipment and that being designed. As a Chinese next-step tokamak, the Chinese Fusion Engineering Test Reactor（CFETR） has to pay attention to the VDE study with full-fledged numerical codes during its conceptual design. The tokamak simulation code（TSC） is a free boundary time-dependent axisymmetric tokamak simulation code developed in PPPL, which advances the MHD equations describing the evolution of the plasma in a rectangular domain. The electromagnetic interactions between the surrounding conductor circuits and the plasma are solved self-consistently. The TokSys code is a generic modeling and simulation environment developed in GA. Its RZIP model treats the plasma as a fixed spatial distribution of currents which couple with the surrounding conductors through circuit equations. Both codes have been individually used for the VDE study on many tokamak devices, such as JT-60U, EAST, NSTX, DIII-D, and ITER. Considering the model differences, benchmark work is needed to answer whether they reproduce each other＇s results correctly. In this paper, the TSC and TokSys codes are used for analyzing the CFETR vertical instability passive and active controls design simultaneously. It is shown that with the same inputs, the results from these two codes conform with each other.展开更多
For achieving the scientific mission of long pulse and high performance operation,experimental advanced superconducting tokamak（EAST） applies fully superconducting magnet technology and is equiped with high power au...For achieving the scientific mission of long pulse and high performance operation,experimental advanced superconducting tokamak（EAST） applies fully superconducting magnet technology and is equiped with high power auxiliary heating system.Besides RF（Radio Frequency） wave heating,neutral beam injection（NBI） is an effective heating and current drive method in fusion research.NBCD（Neutral Beam Current Drive） as a viable non-inductive current drive source plays an important role in quasi-steady state operating scenario for tokamak.The non-inductive current driven scenario in EAST only by NBI is predicted using the TSC/NUBEAM code.At the condition of low plasma current and moderate plasma density,neutral beam injection heats the plasma effectively and NBCD plus bootstrap current accounts for a large proportion among the total plasma current for the flattop time.展开更多
基金supported by the National Natural Science Foundation of China(Grant Nos.11305216,11305209,and 11375191)the National Magnetic Confinement Fusion Research Program of China(Grant Nos.2014GB103000 and 2014GB110003)External Cooperation Program of BIC,Chinese Academy of Sciences(Grant No.GJHZ201303)
文摘Vertical displacement event（VDE） is a big challenge to the existing tokamak equipment and that being designed. As a Chinese next-step tokamak, the Chinese Fusion Engineering Test Reactor（CFETR） has to pay attention to the VDE study with full-fledged numerical codes during its conceptual design. The tokamak simulation code（TSC） is a free boundary time-dependent axisymmetric tokamak simulation code developed in PPPL, which advances the MHD equations describing the evolution of the plasma in a rectangular domain. The electromagnetic interactions between the surrounding conductor circuits and the plasma are solved self-consistently. The TokSys code is a generic modeling and simulation environment developed in GA. Its RZIP model treats the plasma as a fixed spatial distribution of currents which couple with the surrounding conductors through circuit equations. Both codes have been individually used for the VDE study on many tokamak devices, such as JT-60U, EAST, NSTX, DIII-D, and ITER. Considering the model differences, benchmark work is needed to answer whether they reproduce each other＇s results correctly. In this paper, the TSC and TokSys codes are used for analyzing the CFETR vertical instability passive and active controls design simultaneously. It is shown that with the same inputs, the results from these two codes conform with each other.
基金supported by National Natural Science Foundation of China(Nos.11175211,11247302)
文摘For achieving the scientific mission of long pulse and high performance operation,experimental advanced superconducting tokamak（EAST） applies fully superconducting magnet technology and is equiped with high power auxiliary heating system.Besides RF（Radio Frequency） wave heating,neutral beam injection（NBI） is an effective heating and current drive method in fusion research.NBCD（Neutral Beam Current Drive） as a viable non-inductive current drive source plays an important role in quasi-steady state operating scenario for tokamak.The non-inductive current driven scenario in EAST only by NBI is predicted using the TSC/NUBEAM code.At the condition of low plasma current and moderate plasma density,neutral beam injection heats the plasma effectively and NBCD plus bootstrap current accounts for a large proportion among the total plasma current for the flattop time.
