Search Results - "Mau, T.K"

The ARIES-AT advanced tokamak, Advanced technology fusion power plant by Najmabadi, Farrokh, Abdou, A., Bromberg, L., Brown, T., Chan, V.C., Chu, M.C., Dahlgren, F., El-Guebaly, L., Heitzenroeder, P., Henderson, D., St. John, H.E., Kessel, C.E., Lao, L.L., Longhurst, G.R., Malang, S., Mau, T.K., Merrill, B.J., Miller, R.L., Mogahed, E., Moore, R.L., Petrie, T., Petti, D.A., Politzer, P., Raffray, A.R., Steiner, D., Sviatoslavsky, I., Synder, P., Syaebler, G.M., Turnbull, A.D., Tillack, M.S., Waganer, L.M., Wang, X., West, P., Wilson, P.

“…The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant and to…”
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Physics basis for a spherical torus power plant by Jardin, S.C., Kessel, C.E., Menard, J., Mau, T.K., Miller, R., Najmabadi, F., Chan, V.S., Lao, L.L., Linliu, Y.R., Miller, R.L., Petrie, T., Politzer, P.A., Turnbull, A.D.

“…The spherical torus, or low-aspect-ratio tokamak, is considered as the basis for a fusion power plant. A special class of wall-stabilized high- β…”
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Physics basis for a tokamak fusion power plant by Jardin, S.C., Bathke, C.G., Ehst, D.A., Kaye, S.M., Kessel, C.E., Lee, B.J., Mau, T.K., Menard, J., Miller, R., Najmabadi, F.

“…The five ARIES designs, which correspond to five different tokamak operating modes, are reviewed and compared. Physics figures of merit are introduced that…”
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Inferring oscillator’s phase and amplitude response from a scalar signal exploiting test stimulation by Cestnik, Rok, Mau, Erik T K, Rosenblum, Michael

“…Abstract The phase sensitivity curve or phase response curve (PRC) quantifies the oscillator’s reaction to stimulation at a specific phase and is a primary…”
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Accommodation of prompt alpha-particle loss in a compact stellarator power plant by Raffray, A.R., Mau, T.K., Najmabadi, F.

“…Alpha loss is an important issue in stellarators, where the inherent non-axisymmetry of the magnetic geometry causes an appreciable magnetic field ripple along…”
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Plasma profile and shape optimization for the advanced tokamak power plant, ARIES-AT by Kessel, C.E., Mau, T.K., Jardin, S.C., Najmabadi, F.

“…An advanced tokamak plasma configuration is developed based on equilibrium, ideal MHD stability, bootstrap current analysis, vertical stability and control,…”
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Physics basis for the advanced tokamak fusion power plant, ARIES-AT by Jardin, S.C., Kessel, C.E., Mau, T.K., Miller, R.L., Najmabadi, F., Chan, V.S., Chu, M.S., LaHaye, R., Lao, L.L., Petrie, T.W., Politzer, P., St.John, H.E., Snyder, P., Staebler, G.M., Turnbull, A.D., West, W.P.

“…The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A ≡ R / a = 4.0 , an elongation and…”
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The National Transport Code Collaboration Module Library by Kritz, A.H., Bateman, G., Kinsey, J., Pankin, A., Onjun, T., Redd, A., McCune, D., Ludescher, C., Pletzer, A., Andre, R., Zakharov, L., Lodestro, L., Pearlstein, L.D., Jong, R., Houlberg, W., Strand, P., Wiley, J., Valanju, P., John, H.St, Waltz, R., Mandrekas, J., Mau, T.K., Carlsson, J., Braams, B.

“…This paper reports on the progress in developing a library of code modules under the auspices of the National Transport Code Collaboration (NTCC). Code modules…”
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Physics basis for a reversed shear tokamak power plant by Jardin, S.C., Kessel, C.E., Bathke, C.G., Ehst, D.A., Mau, T.K., Najmabadi, F., Petrie, T.W.

“…The reversed shear plasma configuration is examined as the basis for a tokamak fusion power plant. Analysis of plasma equilibrium and ideal MHD stability,…”
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Exploratory Divertor Heat Load Studies for Compact Stellarator Reactors by Mau, T.K., McGuinness, H., Grossman, A., Raffray, A.R., Steiner, D.

“…Divertor heat load evaluation studies are being carried out for an example compact stellarator reactor configuration modeled after the National Compact…”
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Divertor Heat Loads from Thermal and Alpha Particles in a Compact Stellarator Reactor by Mau, T.K., Kaiser, T.B., Lyon, J.F., Maingi, R., Raffray, A.R., Wang, X., Ku, L.P., Zarnstorff, M.

“…Divertor heat load distributions due to thermal and alpha particles have been assessed in an NCSX-based compact stellarator reactor. A divertor plate system is…”
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The current drive and heating systems for the ARIES-RS tokamak power plant by Mau, T.K.

“…The ARIES-RS reversed-shear tokamak power plant was designed with /spl beta/=5% and a high bootstrap current fraction of 88%. Three RF current drive systems…”
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Initial operation of the NSTX phased array for launching high harmonic fast waves by Ryan, P.M, Wilson, J.R, Swain, D.W, Pinsker, R.I, Carter, M.D, Gates, D, Hosea, J.C, Mau, T.K, Menard, J.E, Mueller, D, Sabbagh, S.A, Wilgen, J.B

“…A high harmonic fast wave (HHFW) antenna array, designed to provide up to 6 MW of power at 30 MHz for heating and current drive applications, has been operated…”
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Results of NSTX heating experiments by Mueller, D., Ono, M., Bell, M.G., Bell, R.E., Bitter, M., Bourdelle, C., Darrow, D.S., Efthimion, P.C., Fredrickson, E.D., Gates, D.A., Goldston, R.J., Grisham, L.R., Hawryluk, R.J., Hill, K.W., Hosea, J.C., Jardin, S.C., Ji, H., Kaye, S.M., Kaita, R., Kugel, H.W., Johnson, D.W., LeBlanc, B.P., Majeski, R., Mazzucato, E., Medley, S.S., Menard, J.E., Park, H.K., Paul, S.F., Phillips, C.K., Redi, M.H., Rosenberg, A.L., Skinner, C.H., Soukhanovskii, V.A., Stratton, B., Synakowski, E.J., Taylor, G., Wilson, J.R., Zweben, S.J., Dorland, W.D., Peng, Y.K.M., Barry, R., Bigelow, T., Bush, C.E., Carter, M., Maingi, R., Menon, M., Ryan, P.M., Swain, D.W., Wilgen, J., Sabbagh, S.A., Paoletti, F., Bialek, J., Zhu, W., Raman, R., Jarboe, T.R., Nelson, B.A., Maqueda, R.J., Wurden, G.A., Pinsker, R.I., Schaffer, M., Ferron, J., Lao, L., Stutman, D., Finkenthal, M., Wampler, W., Kubota, S., Peebles, W.A., Gilmore, M., Mau, T.K., Lee, K.C., Domier, C.W., Deng, B.H., Johnson, M., Luhmann, N.C., Bonoli, P., Bers, A., Ram, A., Akers, R., Takase, Y., Ejiri, A., Ono, Y., Shiraiwa, S., Nishino, N., Mitarai, O., Nagata, M., Yang, J.G., Na, H., Pacella, D.

“…The National Spherical Torus Experiment (NSTX) at Princeton University, Princeton, NJ, is designed to assess the potential of the low-aspect-ratio spherical…”
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Configuration and engineering design of the ARIES-RS tokamak power plant by Tillack, M.S, Malang, S, Waganer, L, Wang, X.R, Sze, D.K, El-Guebaly, L, Wong, C.P.C, Crowell, J.A, Mau, T.K, Bromberg, L

“…ARIES-RS is a conceptual design study which has examined the potential of an advanced tokamak-based power plant to compete with future energy sources and play…”
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Initial assessment of an EC heating scenario and system for a compact stellarator power plant by Mau, T.K.

“…The ARIES Advanced System Group has initiated a three-year study of compact stellarators as fusion power plants. Initial assessment was carried out of an…”
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Advanced tokamak scenarios for the FIRE burning plasma experiment by Kessel, C.E., Ignat, D., Mau, T.K.

“…The advanced tokamak capability of the FIRE burning plasma experiment is examined with 0D systems analysis, equilibrium and ideal MHD stability, RF current…”
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Laser-induced damage of metal mirrors under long-term exposure at shallow angle of incidence by Zaghloul, M.R., Tillack, M.S., Mau, T.K.

“…Laser induced damage (LID) experiments were performed with a 2-J frequency-multiplied Nd:YAG laser at 1/2 /spl mu/m wavelength and a variety of metal mirrors…”
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Modeling of mirror surface damage effects on beam performance in a laser-driven IFE power plant by Mau, T.K., Tillack, M.S., Zaghloul, M.R.

“…Grazing incidence metal mirrors in laser-driven IFE power plants are subject to a variety of threats that result in damages leading to increased laser…”
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Plasma system requirements and performance data base for the Starlite/Demo fusion power plant by Mau, T.K., Ehst, D.A., Jardin, S.C., Kessel, C.E., Lee, B.J.

“…General plasma system requirements for the U.S. Demo fusion power plant have been identified, taking into account factors of economics, operability and…”
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