Search Results - "Citrolo, J.C."

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  1. 1

    The TPX superconducting magnet fabrication process by Citrolo, J.C., Chrzanowski, J., Schultz, J.

    “…The TPX Toroidal Field (TF) and Poloidal Field (PF) Coils use both Nb/sub 3/Sn and Nb-Ti internally cooled, cabled superconductor (ICCS). A prime consideration…”
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    Conference Proceeding
  2. 2

    Superconducting magnet system for the TPX Tokamak by Hassenzahl, W.V., Chaplin, M.R., Heim, J.R., Lang, D.D., O'Connor, T.G., Slack, D.S., Wong, R.L., Zbasnik, J.P., Brown, T.G., Citrolo, J.C., Montgomery, D.B., Myatt, L., Pillsbury, R.D., Schultz, J.H., Wang, P.W.

    Published in IEEE transactions on magnetics (01-07-1994)
    “…The Tokamak Physics Experiment (TPX) will be the first Tokamak using superconducting magnets for both the poloidal and toroidal field. It is designed for…”
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    Journal Article Conference Proceeding
  3. 3

    Towards Fusion Reactor Ignition the Adiabatic Toroidal Compression System by Citrolo, J. C.

    Published in IEEE transactions on nuclear science (01-01-1973)
    “…A major problem area in the study of the feasibility of fusion reactors is the attainment of hot dense plasma for experimental study and the determination of a…”
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    Journal Article
  4. 4

    TPX superconducting cable-in-conduit 1995 design and development progress by Zbasnik, J.P., Martovetsky, N.N., Hibbs, S.M., Schultz, J.H., Pillsbury, R.D., Citrolo, J.C.

    “…A unique feature of the magnet system for the Tokamak Physics Experiment (TPX) is that all the magnets are superconducting. With the exception of the outer…”
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    Conference Proceeding
  5. 5

    The TPX magnet R&D program by Zbasnik, J.P., Hassenzahl, W.V., Chaplin, M.R., Slack, D., Lang, D.D., Schultz, J.H., Citrolo, J.C.

    “…A unique feature of the magnet system for the Tokamak Physics Experiment (TPX) is that all the magnets are superconducting. With the exception of the outer…”
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    Conference Proceeding
  6. 6

    The CIT toroidal field coil and structure design and assembly approach by Pusateri, J.A., Citrolo, J.C.

    “…The Compact Ignition Tokamak (CIT) toroidal field (TF) coils are capable of providing an 11-T field at a plasma major radius of 2.1 m. The plasma current will…”
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    Conference Proceeding
  7. 7

    The Vacuum Design for ATC by Citrolo, J. C., Mullaney, D. H.

    Published in IEEE transactions on nuclear science (01-01-1971)
    “…The parameters for the design of vacuum vessels for plasma physics experiments usually are base pressure required, plasma volume, and the geometry of the…”
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    Journal Article
  8. 8

    Confining Field Coils for ATC by Citrolo, J. C., Johnson, H. G., Linton, T. W.

    Published in IEEE transactions on nuclear science (01-01-1971)
    “…This paper describes the engineering design and fabrication of the 24 wedge-shaved coils that produce the toroidal confining field for the ATC machine. The…”
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    Journal Article