Search Results - Schleicher, R.W.

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  1. 1
    Evaluation of U.S. Demo helium-cooled blanket options

    Evaluation of U.S. Demo helium-cooled blanket options by Wong, C.P.C., McQuillan, B.W., Schleicher, R.W., Cheng, E.T.

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    Limitations of power conversion systems under transient loads and impact on the pulsed tokamak power reactor

    Limitations of power conversion systems under transient loads and impact on the pulsed tokamak power reactor by Sager, G.T., Wong, C.P.C., Kapich, D.D., McDonald, C.F., Schleicher, R.W.

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  3. 3
    A robust helium-cooled shield/blanket design for ITER

    A robust helium-cooled shield/blanket design for ITER by Wong, C.P.C., Bourque, R.F., Baxi, C.B., Colleraine, A.P., Grunloh, H.J., Lechtenberg, T., Leuer, J.A., Reis, E.E., Redler, K., Will, R., DelBene, V., Inamati, S.B., Kapich, D.D., Kissinger, J.A., Lewis, A.C., Pickering, J.L., Rao, R., Ryder, R.H., Schleicher, R.W.

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