Disruption Analysis of the Proposed K-DEMO Inner Blanket Support Structure
Authors: Peter H. Titus, H. Neilson, T. Brown, K. Kim
Abstract: The Korean fusion demonstration reactor (K-DEMO) is in the early stages of conceptual design. In one structural concept being considered for K-DEMO a semipermanent inboard shield is employed that also serves as support for the inner blanket modules. The inboard blanket structure and the outboard blanket structure are toroidally electrically continuous and are structurally connected. The inboard modules are keyed into the toroidally continuous support structure which reacts disruption loads from the blankets and from its own internal eddy currents. This arrangement is a part of a vertical maintenance concept, that removes the inboard blanket module components with a radial and vertical traverse and leaves much of the massive shielding and support structure in place. It is important to show the disruption loads can be carried by the proposed structure. The analysis employs a simple modeling of the plasma by adjusting current densities in regions of the cross section defined for the plasma. Vertical translations can be modeled with decreases in plasma regions at the mid plane while increasing current densities in a lower volume. The quench is modeled as a decay of the plasma current. Details of the blankets are developing. The intention of this analysis is to develop a tractable model to investigate basic sizing and feasibility of the inboard
and outboard shield and blanket support concepts and not to rigorously simulate the disruption.
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Submitted to: Physics of Plasmas
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Download PPPL-5122 (pdf 5.7 MB 5pp)
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