Search Results - "Messadek, K."

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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Status of “TITAN” Task 1–3 “Flow Control and Thermofluid Modeling” by Smolentsev, S., Kunugi, T., Messadek, K., Yokomine, T., Young, J., Yuki, K., Ueki, Y., Sketchley, T., Li, F.-C., Morley, N., Abdou, M.

“…► Current accomplishments and ongoing work in Task 1–3 “Flow Control and Thermofluid Modeling” of the US-Japan “TITAN” Program have been reviewed. ► A new MHD…”
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Magnetohydrodynamic flow in ferromagnetic pipes by Bühler, L., Messadek, K., Stieglitz, R.

“…The major part of the magnetohydrodynamic pressure drop in the European water cooled concept for a fusion blanket arises in circular pipes which distribute the…”
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MHD pressure drop in ferritic pipes of fusion blankets by Reimann, J., Bühler, Leo, Messadek, K., Stieglitz, R.

“…Magnetohydrodynamic flows in pipes of ferromagnetic material is an important issue for liquid metal blanket concepts using MANET as wall material. Fusion…”
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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)…”
Get full text

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)…”
Get full text