Physics basis and design of the ITER plasma-facing components von Pitts, R.A., Carpentier, S., Escourbiac, F., Hirai, T., Komarov, V., Kukushkin, A.S., Lisgo, S., Loarte, A., Merola, M., Mitteau, R., Raffray, A.R., Shimada, M., Stangeby, P.C.

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Review of blanket designs for advanced fusion reactors von Ihli, T., Basu, T.K., Giancarli, L.M., Konishi, S., Malang, S., Najmabadi, F., Nishio, S., Raffray, A.R., Rao, C.V.S., Sagara, A., Wu, Y.

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High heat flux components—Readiness to proceed from near term fusion systems to power plants von Raffray, A.R., Nygren, R., Whyte, D.G., Abdel-Khalik, S., Doerner, R., Escourbiac, F., Evans, T., Goldston, R.J., Hoelzer, D.T., Konishi, S., Lorenzetto, P., Merola, M., Neu, R., Norajitra, P., Pitts, R.A., Rieth, M., Roedig, M., Rognlien, T., Suzuki, S., Tillack, M.S., Wong, C.

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Recent US activities on advanced He-cooled W-alloy divertor concepts for fusion power plants von Tillack, M.S., Raffray, A.R., Wang, X.R., Malang, S., Abdel-Khalik, S., Yoda, M., Youchison, D.

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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 (HCL... von Malang, S., Raffray, A.R., Morley, N.B.

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Recent research and development for the dual-coolant blanket concept in the US von Morley, N.B., Katoh, Y., Malang, S., Pint, B.A., Raffray, A.R., Sharafat, S., Smolentsev, S., Youngblood, G.E.

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Optimizing the overall configuration of a He-cooled W-alloy divertor for a power plant von Raffray, A.R., Malang, S., Wang, X.

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The ITER blanket system design challenge von Raffray, A.R., Calcagno, B., Chappuis, P., Fu, Zhang, Furmanek, A., Jiming, Chen, Kim, D-H., Khomiakov, S., Labusov, A., Martin, A., Merola, M., Mitteau, R., Sadakov, S., Ulrickson, M., Zacchia, F.

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Multi-dimensional computational model of the movement of the solid–gas interface during the layering process in inertial confinement fusion targets in a non-uniform thermal environ... von Boehm, K.-J., Raffray, A.R.

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Design and performance study of the helium-cooled T-tube divertor concept von Ihli, T., Raffray, A.R., Abdel-Khalik, S.I., Shin, S.

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Findings of the US research needs workshop on the topic of fusion power von Meier, W.R., Raffray, A.R., Kurtz, R.J., Morley, N.B., Reiersen, W.T., Sharpe, P., Willms, S.

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Design and material issues for high performance SiCf/SiC-based fusion power cores von RAFFRAY, A. R, JONES, R, RICCARDI, B, TILLACK, M. S, AIELLO, G, BILLONE, M, GIANCARLI, L, GOLFIER, H, HASEGAWA, A, KATOH, Y, KOHYAMA, A, NISHIO, S

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Modeling results for mass production layering in a fluidized bed von Boehm, K.J., Raffray, A.R., Alexander, N.B., Goodin, D.T.

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Accommodation of prompt alpha-particle loss in a compact stellarator power plant von Raffray, A.R., Mau, T.K., Najmabadi, F.

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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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Progress towards realization of a laser IFE solid wall chamber von Raffray, A.R., Blanchard, J., Latkowski, J., Najmabadi, F., Renk, T., Sethian, J., Sharafat, S., Snead, L.

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Major integration issues in evolving the configuration design space for the ARIES-CS compact stellarator power plant von Raffray, A.R., Malang, S., El-Guebaly, L., Ihli, T., Najmabadi, F., Wang, X.

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Advanced power core system for the ARIES-AT power plant von Raffray, A.R., El-Guebaly, L., Malang, S., Sviatoslavsky, I., Tillack, M.S., Wang, X.

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Direct drive target survival during injection in an inertial fusion energy power plant von Petzoldt, R.W, Goodin, D.T, Nikroo, A, Stephens, E, Siegel, N, Alexander, N.B, Raffray, A.R, Mau, T.K, Tillack, M, Najmabadi, F, Krasheninnikov, S.I, Gallix, R

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Calculation and superimposition of electro-magnetic loads on the ITER blanket: Analysis strategy and initial results von Rozov, V.O., Raffray, A.R., Lamzin, E.A., Roccella, R., Sugihara, M., Sytchevsky, S.E., Ulrickson, M.A.

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