Speaker
Peter Titus
(Analysis Branch Mechanical Engineering Division)
Description
The Korean fusion demonstration reactor (K-DEMO) is in the early stages of conceptual design. Ceramic breeder blanket modules are being investigated. These have had extensive nuclear and thermal evaluations. Structural assessments are in process. This paper presents stress analyses performed at PPPL in support of the blanket design. Disruption loading, including the effects of ferromagnetic structural materials is evaluated. An approximate, but representative model of the blanket is used to evaluate a full set of normal thermal , pressure, and static magnetic loads. Disruption and faulted pressure loads are assessed as well. Inner and outer support shells are planned. The support shells serve as nuclear and electromagnetic shields for the vessel . 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. Normal and Disruption blanket loads need to be quantified to show that these loads can be carried by the proposed structure, and to qualify the internals of the blanket modules. . The KDEMO disruption analysis employs a simple modeling of the plasma by adjusting current densities in regions of the cross section defined for the plasma. The quench is modeled as a decay of the plasma current. Details of the blankets are developed from published descriptions of the KDEMO ceramic breeder concept. Disruption eddy current loading is quantified by imposing time dependent vector potential gradients from the simplified global disruption model on a more detailed representation of the blanket structure. The intention of this analysis is to develop tractable models of the blankets to investigate basic sizing and feasibility of the inboard and outboard blankets and their support mechanisms.
Co-author
Peter Titus
(Analysis Branch Mechanical Engineering Division, Princeton Plasma Physics Laboratory, Princeton, NJ, United States)
