Search Results - "Sviatoslavsky, I"

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    Fusion power core engineering for the ARIES-ST power plant by Tillack, M.S, Wang, X.R, Pulsifer, J, Malang, S, Sze, D.K, Billone, M, Sviatoslavsky, I

    Published in Fusion engineering and design (01-02-2003)
    “…ARIES-ST is a 1000 MWe fusion power plant based on a low aspect ratio ‘spherical torus’ (ST) plasma. The ARIES-ST power core was designed to accommodate the…”
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    Journal Article
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    Advanced power core system for the ARIES-AT power plant by Raffray, A.R., El-Guebaly, L., Malang, S., Sviatoslavsky, I., Tillack, M.S., Wang, X.

    Published in Fusion engineering and design (01-02-2007)
    “…The ARIES-AT power core was evolved with the overall objective of achieving high performance while maintaining attractive safety features, credible maintenance…”
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    Journal Article
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    High performance blanket for ARIES-AT power plant by Raffray, A.R, El-Guebaly, L, Gordeev, S, Malang, S, Mogahed, E, Najmabadi, F, Sviatoslavsky, I, Sze, D.K, Tillack, M.S, Wang, X

    Published in Fusion engineering and design (01-11-2001)
    “…The ARIES-AT blanket has been developed with the overall objective of achieving high performance while maintaining attractive safety features, simple design…”
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    Journal Article Conference Proceeding
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    Advanced power core system for the ARIES-AT power plant by Raffray, A.R., El-Guebaly, L., Malang, S., Sviatoslavsky, I., Tillack, M.S., Wang, X.

    Published in Fusion engineering and design (2006)
    “…The ARIES-AT power core was evolved with the overall objective of achieving high performance while maintaining attractive safety features, credible maintenance…”
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    Journal Article
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    Molten salt self-cooled solid first wall and blanket design based on advanced ferritic steel by Wong, C.P.C., Malang, S., Sawan, M., Sviatoslavsky, I., Mogahed, E., Smolentsev, S., Majumdar, S., Merrill, B., Mattas, R., Friend, M., Bolin, J., Sharafat, S.

    Published in Fusion engineering and design (01-11-2004)
    “…As an element in the U.S. Advanced Power Extraction (APEX) program, the solid first wall and blanket design team assessed innovative design configurations with…”
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    Journal Article
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    ALPS–advanced limiter-divertor plasma-facing systems by Mattas, R.F, Allain, J.P, Bastasz, R, Brooks, J.N, Evans, T, Hassanein, A, Luckhardt, S, McCarthy, K, Mioduszewski, P, Maingi, R, Mogahed, E, Moir, R, Molokov, S, Morely, N, Nygren, R, Rognlien, T, Reed, C, Ruzic, D, Sviatoslavsky, I, Sze, D, Tillack, M, Ulrickson, M, Wade, P.M, Wooley, R, Wong, C

    Published in Fusion engineering and design (01-11-2000)
    “…The advanced limiter-divertor plasma-facing systems (ALPS) program was initiated in order to evaluate the potential for improved performance and lifetime for…”
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    Journal Article Conference Proceeding
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    APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design by Wong, C.P.C, Malang, S, Sawan, M, Sviatoslavsky, I, Mogahed, E, Smolentsev, S, Majumdar, S, Merrill, B, Mattas, R, Friend, M, Bolin, J, Sharafat, S

    Published in Journal of nuclear materials (01-08-2004)
    “…As an element in the US Advanced Power Extraction (APEX) program, we evaluated the design option of using advanced nanocomposite ferritic steel (AFS) as the…”
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    Journal Article
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    Engineering and geometric aspects of the solid wall re-circulating fluid blanket based on advanced ferritic steel by Sviatoslavsky, I.N., Sawan, M.E., Mogahed, E.A., Majumdar, S., Mattas, R., Malang, S., Fogarty, P.J., Friend, M., Wong, C.P.C., Sharafat, S.

    Published in Fusion engineering and design (01-11-2004)
    “…The Advanced Power Extraction (APEX) project has been exploring concepts for power producing blankets that can enhance the potential of fusion energy. The…”
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    Journal Article
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    Dry wall chamber issues for the SOMBRERO laser fusion power plant by Kulcinski, G.L, Peterson, R.R, Wittenberg, L.J, Mogahed, E.A, Sviatoslavsky, I.N

    Published in Fusion engineering and design (2002)
    “…A reassessment of the SOMBRERO laser driven fusion power plant that was designed in 1990–91 has been conducted. New information and analysis has confirmed most…”
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    Journal Article Conference Proceeding
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    Study of a spherical torus based volumetric neutron source for nuclear technology testing and development by Cheng, E.T, Cerbone, R.J, Sviatoslavsky, I.N, Galambos, L.D, Peng, Y.-K.M

    Published in Fusion engineering and design (01-09-2000)
    “…A plasma based, deuterium and tritium (DT) fueled, volumetric 14 MeV neutron source (VNS) has been considered as a possible facility to support the development…”
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    Journal Article Conference Proceeding
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    ARIES-ST plasma-facing component design and analysis by Tillack, M.S, Wang, X.R, Pulsifer, J, Sviatoslavsky, I

    Published in Fusion engineering and design (01-11-2000)
    “…ARIES-ST is a 1000 MW fusion power plant conceptual design based on a low aspect ratio ‘spherical torus’ (ST) plasma. The plasma-facing components include the…”
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    Journal Article Conference Proceeding
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    ARIES-RS divertor system selection and analysis by Wong, C.P.C, Chin, E, Petrie, T.W, Reis, E.E, Tillack, M, Wang, X, Sviatoslavsky, I, Malang, S, Sze, D.K

    Published in Fusion engineering and design (01-12-1997)
    “…The ARIES-RS divertor system is selected and analyzed. A radiative divertor approach using Ne as the radiator is chosen to reduce the maximum heat flux to <6…”
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    Journal Article
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    Mechanical design considerations of the centerpost for a spherical torus volumetric neutron source by Sviatoslavsky, I.N, Cheng, E.T, Cerbone, R.J, Peng, Y.-K.M, Galambos, J.D, Strickler, D.J, Wang, X.R

    Published in Fusion engineering and design (1999)
    “…The mechanical and thermal design issues of the centerpost (CP) for a spherical torus based volumetric neutron source (ST-VNS) is described. It is intended to…”
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    Journal Article Conference Proceeding
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    Spherical torus concept as power plants—the ARIES-ST study by Najmabadi, F

    Published in Fusion engineering and design (01-02-2003)
    “…Recent experimental achievements and theoretical studies have generated substantial interest in the spherical torus concept. The ARIES-ST study was undertaken…”
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    Journal Article
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    Magnets for the tandem mirror fusion power reactor WITAMIR-I by Maurer, W., Larbalestier, D., Sviatoslavsky, I.

    Published in IEEE transactions on magnetics (01-09-1981)
    “…The design of the magnet system for the Tandem Mirror Fusion Power Reactor WITAMIR-I is presented. The central cell of this reactor consists of 34 dc solenoid…”
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    Journal Article
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    The ARIES-RS power core—recent development in Li/V designs by Sze, Dai-Kai, Billone, Michael C., Hua, Thanh Q., Tillack, Mark, Najmabadi, Farrokh, Wang, Xueren, Malang, Siegfried, El-Guebaly, Laila A., Sviatoslavsky, Igor N., Blanchard, James P., Crowell, Jeffrey A., Khater, Hesham Y., Mogahed, Elsayed A., Waganer, Lester M., Lee, Dennis, Cole, Dick

    Published in Fusion engineering and design (01-09-1998)
    “…The ARIES-RS fusion power plant design study is based on reversed-shear (RS) physics with a Li/V (lithium breeder and vanadium structure) blanket. The…”
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    Journal Article Conference Proceeding
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    Preliminary magnet design for a stellarator fusion reactor by Van Sciver, S., Derr, J., Khalil, A., Sviatoslavsky, I.

    Published in IEEE transactions on magnetics (01-09-1981)
    “…Conceptual design of the superconducting magnets for a stellarator fusion power reactor UWTOR-M are presented. The emphasis in the magnet design is toward…”
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    Journal Article
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    A toroidal field magnet system for NUWMAK by Hong, S., Michaelson, P., Sviatoslavsky, I., Young, W., Boom, R.

    Published in IEEE transactions on magnetics (01-01-1979)
    “…A conceptual design of a toroidal field coil system is presented for NUWMAK, a compact fusion power reactor. The magnet major radius is 5.13 meters, the minor…”
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    Journal Article
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