Abstract
• Description of blanket integration concept. • Stress calculation of breeding blanket segments. • Prediction of Breeding blanket deformation. • Identification of custom-machining concept and prediction of achievable tolerances. • Overview of the various integration issues associated with the design of in-vessel components. The DEMO tokamak architecture is based on large vertical breeding blanket (BB) segments that are accessed from a maintenance hall above the tokamak and are vertically replaced through large upper ports of the vacuum vessel (VV). The feasibility of the BB segments mechanical supports is a prerequisite of this vertical segment architecture. Their design directly impacts on the removal kinematics and the remote handling operations required for release and engagement. The supports must withstand large forces acting on the BB in particular due to electromagnetic (EM) loads. At the same time, they must ensure a sufficiently precise positioning of the BB first wall. Their design also takes into account the significant thermal expansion of the blanket segments that are operated at high temperature avoiding excessive support reaction forces. The BB support concept described in this article does not require fasteners or electrical straps to the VV and therefore much reduces the complexity of the BB remote replacement – a valuable characteristic that would make this concept a milestone in meeting one of the goals defined for the DEMO project: to develop a maintainable fusion power plant design [1] . Each blanket segment is individually supported by the VV without any physical contact to the other blankets or in-vessel components. It relies instead on vertical pre-compression inside the VV due to obstructed thermal expansion and radial pre-compression due to the ferromagnetic force acting on the BB material in the toroidal magnetic field. The verification process did not identify show stoppers. Nonetheless, a further evolution of the concept is required including design improvements to mitigate the high stress levels found in the inboard blankets during plasma disruptions. The fact that no excessively high support reaction forces or large BB deflections were found suggests though that the further development of the concept could be successful.
Highlights
A tokamak architecture based on large vertical blanket segments was – to the authors’ best knowledge - first proposed in the early 80s for INTOR [2], adopted in NET [3], in the first concept of ITER [4], and in the European power plant conceptual studies [5]
They may occur due to the following phenomena: (i) interaction of the magnetic field with the breeding blanket (BB) ferromagnetic steel mainly causing forces in radial direction due to the toroidal field gradient, (ii) currents induced in the BB segments as a consequence of magnetic field variations, mainly due to a TFCFD, a plasma thermal quench or a plasma current quench (CQ), and (iii) currents from the plasma halo region running in the BB during vertical displacement events (VDEs)
Argentinian results of material irradiation indicate a decrease of the saturation of the magnetization of up to 30% due to neutron irradiation with fluences several orders of magnitude lower than what is expected in DEMO [37]
Summary
A tokamak architecture based on large vertical blanket segments was – to the authors’ best knowledge - first proposed in the early 80s for INTOR [2], adopted in NET [3], in the first concept of ITER [4], and in the European power plant conceptual studies [5]. This architecture aims at reducing the number of in-vessel components (IVCs) and their replacement duration and allows using a crane-like device to lift the heavy breeding blanket (BB) segments. The basic principle of the BB attachment concept that is presented here was first introduced in [6] and has been partially verified previ ously based on a number of assumptions in [7]
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