Abstract
For the safe operation of Experimental Advanced Superconducting Tokamak (EAST) with higher plasma performance discharge in future, it is important to study the effect of plasma disruption on central solenoid (CS) coils. The outlet temperature rise of CS1-6 coils measured in experiment is analyzed. It is found that the outlet temperature rise of CS1-6 coils caused by plasma disruption cannot be observed in experimental data, because the effect of plasma disruption on outlet of CS coils is a small value, and the discretization error of experimental data is bigger than this value. In addition, the maximum temperature of CS coils during the plasma discharge is simulated by SAITOKPF code, and it appears that the maximum temperature of CS coils increases a little in the plasma disruption, but the temperature rise is a small quantity.
Sign-in/Register to access full text options 
Free) 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a call
