Magnet System Design for Advanced Fusion Devices


The Tokamak Physics Experiment (TPX), a superconducting tokamak which is the next step in the US fusion program, is in a preliminary design phase and awaits approval to begin construction at the Princeton Plasma Physics Laboratory. Some members of our staff have system level engineering responsibilities, and responsibility for the design and R&D for the poloidal field coil subsystem, and for magnet system safety and reliability analyses. Extensive structural and magnetic analyses of the magnet systems have been performed at MIT/PSFC using the ANSYS code.

We have also been engaged in advanced design for the all-superconducting International Thermonuclear Experimental Reactor (ITER). This includes Structural Analysis; conductor design, and R&D; quench simulation, and test; and fault analyses among other responsilities. This facility is proposed for construction during the late 1990s by an international collaborative effort. The peak fields in that device are projected to be 13 tesla, with current densities of 4 kA/cm2, and stored energies of 50 GJ. Engineering teams from all four participating parties (US, RF, EC and Japan) have chosen to design magnets that will be wound using variants of the cable in conduit superconductor (CICC) developed at MIT/PSFC.


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