EAST can provide better opportunities to contribute development of ITER-relevant plasma physics and engineering because it has ITER-like configuration, and has achieved 10s H-mode plasma, and aims steady-state operation of DD high performance plasma. The impact of Test blanket module (TBM) using RAFM (reduced activation ferritic/martensitic) steels on tokomak plasma is a major concern in ITER operations. In order to assess this effect due to TBM local ripple, an experiment plan of TBM mockup using RAFM steel is being planned on MAPES (Material and Plasma Evaluation System) in EAST. This paper reports experimental consideration on MAPES based on magnetic analysis and ripple calculation at separatrix point. The relevant experiments strategy and plan in EAST are also proposed.
- Nuclear Engineering Division
The Experimental Consideration for TBM Mock-Up Effect on Plasma Performance Based on MAPES Platform in EAST
- Views Icon Views
- Share Icon Share
- Search Site
Liu, S, Ding, F, Chen, X, Pu, Y, Li, J, Ma, X, & Luo, G. "The Experimental Consideration for TBM Mock-Up Effect on Plasma Performance Based on MAPES Platform in EAST." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering. Chengdu, China. July 29–August 2, 2013. V005T14A007. ASME. https://doi.org/10.1115/ICONE21-15703
Download citation file: