Structural analysis and manufacture for the vacuum vessel of experimental advanced superconducting tokamak (EAST) device

Abstract

The experimental advanced superconducting tokamak (EAST) is an advanced steady-state plasma physics experimental device, which has been approved by the Chinese government and is being constructed as the Chinese national nuclear fusion research project. The vacuum vessel, that is one of the key components, will have to withstand not only the electromagnetic force due to the plasma disruption and the Halo current, but also the pressure of boride water and the thermal stress due to the 250 °C baking out by the hot pressure nitrogen gas, or the 100 °C hot wall during plasma operation. This paper is a report of the mechanical analyses of the vacuum vessel. According to the allowable stress criteria of American Society of Mechanical Engineers, Boiler and Pressure Vessel Committee (ASME), the maximum integrated stress intensity on the vacuum vessel is 396 MPa, less than the allowable design stress intensity 3 S m (441 MPa). At the same time, some key R & D issues are presented, which include supporting system, bellows and the assembly of the whole vacuum vessel.