Design of Test Platform of High-Payload Transporter Joint for a Tokamak

A general purpose remote-handling system with high-payload handing capability is necessary for Tokamak fusion reactors. Such a system helps maintain in-vessel components that could be damaged by high-temperature plasma. A high-payload transporter has been designed and a key rotary joint has been selected by the ITER Organization. To verify the feasibility of the high-payload transporter in engineering applications, its rotary joints that will be exposed to severe dynamic loads needs to be designed, manufactured, and tested. This system includes a test platform, a control system, and measuring instruments. This article discusses the design, analyses, and principle of the load simulation for the test platform. The mechanical jigs of the test platform are designed, and they consist of the bracket, Oldham coupling, and load shafts. The strength and deformation analyses of the loading shafts are conducted. The equivalent stress of the loading shafts is approximately 285.42 MPa, and the total deflection of joint #4 and the shafts is approximately 10.81 mm. The results show that the mechanical structure of the test platform conforms to the Chinese national standard. Hydraulic cylinders are used to generate the shear force, bending moment, and torque as well as to simulate the payload. The loading principle and method of the hydraulic system are introduced to illustrate that the hydraulic loading scheme can meet the loading requirements. The design scheme satisfies the test requirements, and is confirmed and accepted by the ITER Organization.