Search Results - "Morley, N.B"

Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy by Kessel, C.E., Blanchard, J.P., Davis, A., El-Guebaly, L., Garrison, L.M., Ghoniem, N.M., Humrickhouse, P.W., Huang, Y., Katoh, Y., Khodak, A., Marriott, E.P., Malang, S., Morley, N.B., Neilson, G.H., Rapp, J., Rensink, M.E., Rognlien, T.D., Rowcliffe, A.F., Smolentsev, S., Snead, L.L., Tillack, M.S., Titus, P., Waganer, L.M., Wallace, G.M., Wukitch, S.J., Ying, A., Young, K., Zhai, Y.

“…The Fusion Nuclear Science Facility (FNSF) is examined here as part of a two step program from ITER to commercial power plants. This first step is considered…”
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Numerical simulation of wavy falling film flow using VOF method by Gao, D., Morley, N.B., Dhir, V.

“…Surface wave dynamics of vertical falling films under monochromatic-frequency flowrate-forcing perturbations is computed by the direct simulation of…”
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Fusion materials science and technology research opportunities now and during the ITER era by Zinkle, S.J., Blanchard, J.P., Callis, R.W., Kessel, C.E., Kurtz, R.J., Lee, P.J., McCarthy, K.A., Morley, N.B., Najmabadi, F., Nygren, R.E., Tynan, G.R., Whyte, D.G., Willms, R.S., Wirth, B.D.

“…Several high-priority near-term potential research activities to address fusion nuclear science challenges are summarized. General recommendations include: (1)…”
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Macroscopic motion of liquid metal plasma facing components in a diverted plasma by Jaworski, M.A., Gerhardt, S.P., Morley, N.B., Abrams, T., Kaita, R., Kallman, J., Kugel, H., Majeski, R., Ruzic, D.N.

“…Liquid metal plasma facing components (PFCs) have been identified as an alternative material for fusion plasma experiments. The use of a liquid conductor where…”
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Progress in lattice Boltzmann methods for magnetohydrodynamic flows relevant to fusion applications by Pattison, M.J., Premnath, K.N., Morley, N.B., Abdou, M.A.

“…In this paper, an approach to simulating magnetohydrodynamic (MHD) flows based on the lattice Boltzmann method (LBM) is presented. The dynamics of the flow are…”
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MHD simulations of liquid metal flow through a toroidally oriented manifold by Morley, N.B., Ni, M.-J., Munipalli, R., Huang, P., Abdou, M.A.

“…In fusion liquid metal (LM) blankets, magnetohydrodynamic (MHD) effects will dominate the pressure drop and velocity profiles of the liquid metal flow,…”
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Progress on the modeling of liquid metal, free surface, MHD flows for fusion liquid walls by Morley, N.B., Smolentsev, S., Munipalli, R., Ni, M.-J., Gao, D., Abdou, M.

“…The proposed use of a flowing liquid metal layers as virtual first-walls for magnetic fusion energy reactors has prompted the development of numerical models…”
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An example pathway to a fusion power plant system based on lead–lithium breeder: Comparison of the dual-coolant lead–lithium (DCLL) blanket with the helium-cooled lead–lithium (HCLL) concept as initial step by Malang, S., Raffray, A.R., Morley, N.B.

“…The pathway to the successful development of an attractive power plant implies a successful strategy in developing a number of key fusion systems forming part…”
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A Fusion Nuclear Science Facility for a fast-track path to DEMO by Garofalo, A.M., Abdou, M.A., Canik, J.M., Chan, V.S., Hyatt, A.W., Hill, D.N., Morley, N.B., Navratil, G.A., Sawan, M.E., Taylor, T.S., Wong, C.P.C., Wu, W., Ying, A.

“…•A FNSF is needed to reduce the knowledge gaps to a fusion DEMO and accelerate progress toward fusion energy.•FNSF will test and qualify first-wall/blanket…”
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Overview of liquid metal TBM concepts and programs by Wong, C.P.C., Salavy, J.-F., Kim, Y., Kirillov, I., Rajendra Kumar, E., Morley, N.B., Tanaka, S., Wu, Y.C.

“…In support of the ITER Test Blanket Module (TBM) program and coordinated by the Test Blanket Working Group, ITER party members have been focusing on the liquid…”
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Normal operation and maintenance safety lessons from the ITER US PbLi test blanket module program for a US FNSF and DEMO by Merrill, B.J., Wong, C.P.C., Cadwallader, L.C., Abdou, M., Morley, N.B.

“…A leading power reactor breeding blanket candidate for a fusion demonstration power plant (DEMO) being pursued by the US Fusion Community is the Dual Coolant…”
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Recent research and development for the dual-coolant blanket concept in the US by Morley, N.B., Katoh, Y., Malang, S., Pint, B.A., Raffray, A.R., Sharafat, S., Smolentsev, S., Youngblood, G.E.

“…The dual-coolant lead-lithium, or DCLL, blanket concept is of strong interest in the US fusion technology program. In the DCLL blanket, the flow channel insert…”
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Thermocapillary and thermoelectric effects in liquid lithium plasma facing components by Jaworski, M.A., Morley, N.B., Ruzic, D.N.

“…Recent experiments have renewed interest in the use of liquid lithium as a plasma facing component (PFC). The liquid metal surface will experience a number of…”
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An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design by Wong, C.P.C., Malang, S., Sawan, M., Dagher, M., Smolentsev, S., Merrill, B., Youssef, M., Reyes, S., Sze, D.K., Morley, N.B., Sharafat, S., Calderoni, P., Sviatoslavsky, G., Kurtz, R., Fogarty, P., Zinkle, S., Abdou, M.

“…An attractive blanket concept for the fusion reactor is the dual coolant Pb–17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used…”
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An overview of the US DCLL ITER-TBM program by Wong, C.P.C., Abdou, M., Dagher, M., Katoh, Y., Kurtz, R.J., Malang, S., Marriott, E.P., Merrill, B.J., Messadek, K., Morley, N.B., Sawan, M.E., Sharafat, S., Smolentsev, S., Sze, D.K., Willms, S., Ying, A., Youssef, M.Z.

“…Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM)…”
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Numerical analysis of MHD flow and heat transfer in a poloidal channel of the DCLL blanket with a SiCf/SiC flow channel insert by SMOLENTSEV, S, ABDOU, M, MORLEY, N. B, SAWAN, M, MALANG, S, WONG, C

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Heat Testing of a Prototypical SiC-Foam-Based Flow Channel Insert by Sharafat, S, Aoyama, A, Ghoniem, N, Williams, B, Katoh, Y

“…As part of the U.S. ITER test blanket module development effort, several flow channel insert (FCI) concepts using a variety of porous SiC and SiC/SiC…”
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The influence of a magnetic field on turbulent heat transfer of a high Prandtl number fluid by Nakaharai, H., Takeuchi, J., Yokomine, T., Kunugi, T., Satake, S., Morley, N.B., Abdou, M.A.

“…The influence of a transverse magnetic field on the local and average heat transfer of an electrically conducting, turbulent fluid flow with high Prandtl…”
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Findings of the US research needs workshop on the topic of fusion power by Meier, W.R., Raffray, A.R., Kurtz, R.J., Morley, N.B., Reiersen, W.T., Sharpe, P., Willms, S.

“…The US Department of Energy, Office of Fusion Energy Sciences (OFES) conducted a Research Needs Workshop, referred to as ReNeW, in June 2009. The information…”
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An Overview of the US DCLL ITER TBM Program by Wong, C. P. C., Abdou, M, Dagher, M, Katoh, Yutai, Kurtz, Richard, Malang, Siegfried, Marriott, Edward, Merrill, Brad, Messadek, K, Morley, N.B., Pint, Bruce A, Sawan, M., Sharafat, S, Smolentsev, Sergey, Sze, Dai-Kai, Willms, Scott, Ying, Alice, Youssef, M Z

“…Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM)…”
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