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

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High performance blanket for ARIES-AT power plant von Raffray, A.R, El-Guebaly, L, Gordeev, S, Malang, S, Mogahed, E, Najmabadi, F, Sviatoslavsky, I, Sze, D.K, Tillack, M.S, Wang, X

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Overview of the TITAN project von Muroga, T., Sze, D.K., Okuno, K.

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An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design von 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.

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An overview of the US DCLL ITER-TBM program von 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.

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Helium-cooled refractory alloys first wall and blanket evaluation von Wong, C.P.C, Nygren, R.E, Baxi, C.B, Fogarty, P, Ghoniem, N, Khater, H, McCarthy, K, Merrill, B, Nelson, B, Reis, E.E, Sharafat, S, Schleicher, R, Sze, D.K, Ulrickson, M, Willms, S, Youssef, M, Zinkle, S

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A fusion reactor design with a liquid first wall and divertor von Nygren, R.E., Rognlien, T.D., Rensink, M.E., Smolentsev, S.S., Youssef, M.Z., Sawan, M.E., Merrill, B.J., Eberle, C., Fogarty, P.J., Nelson, B.E., Sze, D.K., Majeski, R.

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Development of advanced blanket performance under irradiation and system integration through JUPITER-II project von Abe, K., Kohyama, A., Tanaka, S., Namba, C., Terai, T., Kunugi, T., Muroga, T., Hasegawa, A., Sagara, A., Berk, S., Zinkle, S.J., Sze, D.K., Petti, D.A., Abdou, M.A., Morley, N.B., Kurtz, R.J., Snead, L.L., Ghoniem, N.M.

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An overview of US ITER test blanket module program von Ying, A., Abdou, M., Wong, C., Malang, S., Morley, N., Sawan, M., Merrill, B., Sze, D.K., Kurtz, R., Willms, S., Ulrickson, M., Zinkle, S.

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Molten salts in fusion nuclear technology von Moriyama, H, Sagara, A, Tanaka, S, Moir, R.W, Sze, D.K

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ARIES-ST safety design and analysis von Khater, H.Y, Mogahed, E.A, Sze, D.K, Tillack, M.S, Wang, X.R

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Technical issues and requirements of experiments and facilities for fusion nuclear technology von Abdou, M.A, Gierszewski, P.J, Tillack, M.S, Nakagawa, M, Reimann, J, Sze, D.K, Bartlit, J, Grover, J, Puigh, R, McGrath, R.T

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Blanket material and engineering issues, and requirements for experiments and facilities von Abdou, M.A., Gierszewski, P., Tillack, M.S., Raffray, A.R., Sze, D.K., Puigh, R.

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EVOLVE—an advanced first wall/blanket system von Mattas, R.F., Malang, S., Khater, H., Majumdar, S., Mogahed, E., Nelson, B., Sawan, M., Sze, D.K.

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Tritium recovery from liquid metals von Moriyama, H, Tanaka, S, Sze, D.K, Reimann, J, Terlain, A

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Configuration and engineering design of the ARIES-RS tokamak power plant von 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

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ARIES-ST breeding blanket design and analysis von Tillack, M.S., Wang, X.R., Pulsifer, J., Malang, S., Sze, D.K.

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ARIES-RS divertor system selection and analysis von Wong, C.P.C, Chin, E, Petrie, T.W, Reis, E.E, Tillack, M, Wang, X, Sviatoslavsky, I, Malang, S, Sze, D.K

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An optimum rankine power cycle for the lithium-cooled TITAN-I reversed-field-pinch reactor von Hasan, Mohammad Z., Sze, D.K.

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Helium processing for deuterium/helium burns in ITER's physics phase von Finn, P.A., Sze, D.K.

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