ITER-hard Toroidal Field coil structural analysis.

摘要

The High Aspect Ratio Design (HARD) for the International Thermonuclear Experimental Reactor (ITER) has Toroidal Field (TF) coils that are farther out from the center of the Toroidal ring and more elongated than the previous design (CDA). These coils should see higher forces than in CDA and were designed accordingly. The objective of this work, conducted at LLNL and the MIT Plasma Fusion Center, was to determine whether stress levels in the ITER-HARD design are acceptable. A global finite element model, representing one of the coils, was modeled at MIT to obtain stresses and displacements both during operation of the TF coils alone, and during the End of Burn phase with TF and PF (Poloidal Field) coils operating. At LLNL, a detail model of the TF coil straight leg near the equator was used to obtain stresses and displacements during TF operation only. Further detailed analysis of the winding pack of this model was done to estimate stress concentrations in the conduit and insulation.