Search Results - "Sviatoslavsky, I.N."

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

“…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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Neutronics Assessment of Blanket Options for the HAPL Laser Inertial Fusion Energy Chamber by Sawan, M.E., Sviatoslavsky, I.N., Raffray, A.R., Wang, X.

“…Three blanket design concepts were evaluated for the High Average Power Laser (HAPL) chamber. These include a self-cooled lithium blanket, a helium-cooled…”
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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.

“…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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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

“…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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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

“…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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3D thermo-mechanical analysis of the ITER limiter small scale specimen by Mogahed, E.A., Sviatoslavsky, I.N.

“…This analysis describes in part, the design activity related to the small scale limiter specimen for ITER. Steady state heat fluxes of 3 MW/m/sup 2/ are…”
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Thermal and structural analysis of the first wall in the SIRIUS-P reactor by Mogahed, E.A., Sviatoslavsky, I.N.

“…The SIRIUS-P conceptual design study is of a 1.0 GWe laser driven inertial confinement fusion power reactor utilizing near symmetric illumination of direct…”
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ARIES-RS loss of coolant accident (LOCA) analysis by Mogahed, E.A., Khater, H., Sviatoslavsky, I.N., El-Guebaly, L.

“…Loss of Coolant Accident (LOCA) analysis has been performed for the ARIES-RS fusion power plant. LOCA occurs when one or more supply tubes outside the reactor…”
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Thermo-mechanical design and structural analysis of the first wall for ARIES-III, a 100 MWe D-/sup 3/He power reactor by Sviatoslavsky, I.N., Blanchard, J.P., Mogahed, E.A.

“…The ARIES-III first wall (FW) is made of a low-activation ferritic steel (MHT-9) and is cooled with an organic coolant (HB-40) at a pressure of 2 MPa. The FW…”
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Mechanical design considerations of 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.

“…The mechanical design of a spherical torus based volumetric neutron source (ST VNS) is being studied under the support of a DOE-SBIR funding. A device capable…”
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Engineering description of a solid first wall blanket based on advanced ferritic steel and re-circulating Flibe by Sviatoslavsky, I.N., Sawan, M.E., Mogahed, E.A., Malang, S., Wong, C.P.C., Friend, M., Majumdar, S., Sharafat, S.

“…A solid wall blanket utilizing advanced ferritic steel and re-circulating Flibe has been scoped out under the Advanced Power Extraction (APEX) program. This…”
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Activation and safety analyses for the D-/sup 3/He fueled tokamak reactor Apollo by Khater, H.Y., Sawan, M.E., Lomperski, S.W., Sviatoslavsky, I.N.

“…An activation analysis was performed for the Apollo D-/sup 3/He-fueled reactor. Three different steel alloys (PCA, 316 SS, and the manganese steel Tenelon)…”
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A novel first wall protection scheme for ion beam ICF reactors by Mogahed, E.A., Cousseau, P.L., Engelstad, R.L., Peterson, R.R., Khater, H.Y., Kulcinski, G.L., MacFarlane, J.J., Wang, P., Sawan, M.E., Sviatoslavsky, I.N., Wittenberg, L.J.

“…A novel first wall protection scheme for ion beam driven inertial confinement fusion reactors is presented. LIBRA-SP utilizes a self-pinched ion beam transport…”
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Energy deposition and first wall response in the SIRIUS-T target chamber by MacFarlane, J.J., Moses, G.A., Peterson, R.R., Sviatoslavsky, I.N.

“…The response of the first wall of the SIRIUS-T inertial confinement fusion (ICF) target chamber to high-gain target explosions has been investigated…”
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Energy conversion options for ARIES-III-a conceptual D-/sup 3/He tokamak reactor by Santarius, J.F., Blanchard, J.P., Emmert, G.A., Sviatoslavsky, I.N., Wittenberg, L.J., Ghoniem, N.M., Hasan, M.Z., Mau, T.K., Greenspan, E., Herring, J.S., Kernbichler, W., Klein, A.C., Miley, G.H., Miller, R.L., Peng, Y.-K.M., Schaffer, M.J., Wong, C.P.C., Steiner, D., Sze, D.-K.

“…High-efficiency energy conversion schemes for a D-/sup 3/He tokamak reactor are investigated. The loss channels for a D-/sup 3/He plasma are through charged…”
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SOMBRERO-a solid breeder moving bed KrF laser driven IFE power reactor by Sviatoslavsky, I.N., Sawan, M.E., Peterson, R.R., Kulcinski, G.L., MacFarlane, J.J., Wittenberg, L.J., Mogahed, E.A., Rutledge, S.C., Ghose, S., Bourque, R.F.

“…SOMBRERO, a conceptual design study of a 1000-MWe KrF laser driven IFE (inertial fusion energy) power reactor utilizing direct drive targets with near…”
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An improved first stability advanced fuel tokamak Apollo-L3 by Emmert, G.A., Kulcinski, G.L., Blanchard, J.P., El-Guebaly, L.A., Khater, H., Maynard, C.W., Mogahed, E.A., Santarius, J.F., Sawan, M.E., Sviatoslavsky, I.N., Wittenberg, L.J.

“…The Apollo-L3 conceptual reactor design utilizes D-/sup 3/He fuel in a first stability tokamak configuration with direct conversion of synchrotron radiation to…”
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LIBRA-LiTE, a light ion inertial confinement fusion reactor with ballistic ion propagation by Peterson, R.R., Englestad, R.L., Kulcinski, G.L., Lovell, E.G., MacFarlane, J.J., Mogahed, E., Moses, G.A., Rutledge, S., Sawan, M.E., Sviatoslavsky, I.N., Sviatoslavsky, G., Wittenberg, L.J.

“…LIBRA-LiTE is a conceptual design for a 1300-MWe power plant using light ion inertial fusion. LIBRA-LiTE differs from the LIBRA design in its use of…”
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Apollo-L2, an advanced fuel tokamak reactor utilizing direct conversion by Emmert, G.A., Kulcinski, G.L., Blanchard, J.P., El-Guebaly, L.A., Khater, H.Y., Santarius, J.F., Sawan, M.E., Sviatoslavsky, I.N., Wittenberg, L.J., Witt, R.J.

“…A scoping study of a tokamak reactor fueled by a D-/sup 3/He plasma is presented. The Apollo D-/sup 3/He tokamak incorporates recent advances in high-field…”
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An aqueous lithium salt blanket for ITER by Sawan, M.E., Sviatoslavsky, I.N., Kulcinski, G.L., Blanchard, J.P., Khater, H.Y., Mogahed, E.A., Wittenberg, L.J.

“…An aqueous lithium salt blanket is designed as a candidate for the tritium production blanket of ITER (International Thermonuclear Experimental Reactor). There…”
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