T.G. O'Connor

Lawrence Livermore National Laboratory, Livermore, California, United States

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Publications (5)4.04 Total impact

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    ABSTRACT: The Tokamak Physics Experiment (TPX) at Princeton will be the first tokamak with an all superconducting poloidal field (PF) magnet system. The conductors are all cable-in-conduit (CICC) superconductors with a single conduit, similar to those in the International Thermonuclear Experimental Reactor (ITER). 10 of the PF coils use Nb<sub>3</sub>Sn superconductor while 4 of them use NbTi. High noise initiation and disruptions demand the use of an advanced quench detection system.
    IEEE Transactions on Applied Superconductivity 07/1995; · 1.20 Impact Factor
  • T.G. O'Connor, J.R. Heim
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    ABSTRACT: The Tokamak Physics Experiment (TPX) concept design uses superconducting coils to accomplish magnetic confinement. The central solenoid (CS) magnet is divided vertical into 8 equal segments which are powered independently. The eddy current heating from the pulsed operation is too high for a case type construction; therefore, a “no case” design has been chosen. This “no case” design uses the conductor conduit as the primary structure and the electrical installation as a structural adhesive. This electrical insulation is the “weak link” in the cell winding pack structure. A global finite element model with smeared winding pack properties was used to study the CS magnet structural behavior. The structural analysis results and peak stresses will be presented
    IEEE Transactions on Magnetics 08/1994; · 1.42 Impact Factor
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    ABSTRACT: The Tokamak Physics Experiment (TPX) will be the first Tokamak using superconducting magnets for both the poloidal and toroidal field. It is designed for advanced Tokamak physics experiments in steady-state and long-pulse operation. The TPX superconducting magnets use an advanced cable-in-conduit conductor (CICC) design similar to that developed in support of the International Thermonuclear Experimental Reactor (ITER). The toroidal field magnets provide 4.0 T at 2.25 m with a stored energy of 1.05 GJ. The poloidal field magnets provide 18.0 V-s to ohmically start and control long burns of a 2.0 MA plasma
    IEEE Transactions on Magnetics 08/1994; · 1.42 Impact Factor
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    ABSTRACT: The Tokamak Physics Experiment (TPX) at Princeton will be the first tokamak with an all superconducting magnet system, including both the toroidal field (TF) and poloidal field (PF) coils. The conductors are all cable-in-conduit (CIC) superconductors with a single conduit, similar to those in the International Thermonuclear Experimental Reactor (ITER)
    Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on; 11/1993
  • T.G. O'Connor, J.P. Zbasnik
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    ABSTRACT: The Tokamak Physics Experiment concept design uses superconducting coils made from cable-in-conduit conductor to accomplish both magnetic confinement and plasma initiation. The Poloidal Field (PF) magnet system is divided into two subsystems, the central solenoid and the outer ring coils, the latter is focus of this paper. The eddy current heating from the pulsed operation is excessive for a case type construction; therefore, a “no case” design has been chosen. This “no case” design uses the conductor conduit as the primary structure and the electrical insulation (fiberglass/epoxy wrap) as a structural adhesive. The model integrates electromagnetic analysis and structural analysis into the finite element code ANSYS to solve the problem. PF coil design is assessed by considering a variety of coil current wave forms, corresponding to various operating modes and conditions. The structural analysis shows that the outer ring coils are within the requirements of the fatigue life and fatigue crack growth requirements. The forces produced by the Toroidal Field coils on the PF coils have little effect on the maximum stresses in the PF coils. In addition in an effort to reduce the cost of the coils a new elongated PF coil design was proposed which changes the aspect ratio of the outer ring coils to reduce the number of turns in the coils. The compressive stress in the outer ring coils is increased while the tensile stress is decreased
    Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on; 11/1993