Both theory and experiment have proved Snowflake configuration could reduce the heat loads on divertor plate. Due to limitation of PF coils, EAST could only operate with quasi-snowflake (QSF). In 2014 EAST campaign, QSF has been achieved by RZIp control. The next important task is the QSF shape control. As tokamak discharge simulation code, Tokamak Simulation Code (TSC), which has been benchmarked by experimental data, is used to simulate EAST QSF discharge. Singular Value Decomposition (SVD) method, a way to decouple the PF current and control parameter, is implemented in TSC code to simulate the course of QSF shape control. The simulation results show SVD method is a good way for EAST QSF shape control.
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering
Guo, Y., Pironti, A., Liu, L., Xiao, B. J., Albanese, R., Ambrosino, R., ... Xing, Z. (2015). Simulation of EAST quasi-snowflake discharge by tokamak simulation code. Fusion Engineering and Design, 101, 101 - 110. https://doi.org/10.1016/j.fusengdes.2015.10.010