Making tungsten work – ICFRM-14 session T26 paper 501 Nygren et al. making tungsten work von Nygren, R.E., Raffray, R., Whyte, D., Urickson, M.A., Baldwin, M., Snead, L.L.

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High heat flux Langmuir probe array for the DIII-D divertor plates von Watkins, J. G., Taussig, D., Boivin, R. L., Mahdavi, M. A., Nygren, R. E.

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Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operation von Kugel, H.W., Bell, M.G., Schneider, H., Allain, J.P., Bell, R.E., Kaita, R., Kallman, J., Kaye, S., LeBlanc, B.P., Mansfield, D., Nygren, R.E., Maingi, R., Menard, J., Mueller, D., Ono, M., Paul, S., Gerhardt, S., Raman, R., Sabbagh, S., Skinner, C.H., Soukhanovskii, V., Timberlake, J., Zakharov, L.E.

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Physics design requirements for the National Spherical Torus Experiment liquid lithium divertor von Kugel, H.W., Bell, M., Berzak, L., Brooks, A., Ellis, R., Gerhardt, S., Harjes, H., Kaita, R., Kallman, J., Maingi, R., Majeski, R., Mansfield, D., Menard, J., Nygren, R.E., Soukhanovskii, V., Stotler, D., Wakeland, P., Zakharov, L.E.

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Preparation of the liquid lithium divertor plates for NSTX von Nygren, R.E., McKee, G.R., Fordham, J.A., Lewis, S.A., Kugel, H., Ellis, R.A., Viola, M.E., O’Dell, J.S.

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High heat flux testing of a helium-cooled tungsten tube with porous foam von Youchison, D.L., Lutz, T.J., Williams, B., Nygren, R.E.

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Comparison of heat flux measurement techniques during the DIII-D metal ring campaign von Barton, J L, Nygren, R E, Unterberg, E A, Watkins, J G, Makowski, M A, Moser, A, Rudakov, D L, Buchenauer, D

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The Sandia Plasma Materials Test Facility in 2007 von McDonald, J.M., Lutz, T.J., Youchison, D.L., Bauer, F.J., Troncosa, K.P., Nygren, R.E.

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Fusion materials science and technology research opportunities now and during the ITER era von 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.

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Recent sheath physics studies on DIII-D von Watkins, J.G., Labombard, B., Stangeby, P.C., Lasnier, C.J., McLean, A.G., Nygren, R.E., Boedo, J.A., Leonard, A.W., Rudakov, D.L.

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Features of plasma sprayed beryllium armor for the ITER first wall von Nygren, R.E., Youchison, D.L., Hollis, K.J.

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Thermal modeling of W rod armor von Nygren, R.E.

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Failure of a lithium-filled target and some implications for fusion components von Nygren, R.E., Youchison, D.L., Michael, J.R., Puskar, J.D., Lutz, T.J.

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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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Testing of a high temperature radiatively cooled Li/Ta heat pipe in Magnum-PSI von Matthews, G.F., Nygren, R.E., Morgan, T.W., Silburn, S.A., Cooper, P.R., Otin, R., Tallarigo, A.

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Considerations in testing of ITER first wall mockups von Tanaka, T.J., Nygren, R.E., Youchison, D.L., Ulrickson, M.A.

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Post-test examination of a Li-Ta heat pipe exposed to H plasma in Magnum PSI von Nygren, R.E., Matthews, G.F., Morgan, T.W., Silburn, S.A., Rosenfeld, J.H., North, M.T., Tallarigo, A., Stavila, V.N.

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Effects of ion beam assisted deposition, beam sharing and pivoting in EB-PVD processing of graded thermal barrier coatings von Youchison, D.L., Gallis, M.A., Nygren, R.E., McDonald, J.M., Lutz, T.J.

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Measurement and modeling of surface temperature dynamics of the NSTX liquid lithium divertor von McLean, A.G., Gan, K.F., Ahn, J.-W., Gray, T.K., Maingi, R., Abrams, T., Jaworski, M.A., Kaita, R., Kugel, H.W., Nygren, R.E., Skinner, C.H., Soukhanovskii, V.A.

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Thermal management of tungsten leading edges in DIII-D von Nygren, R.E., Rudakov, D.L., Murphy, C., Watkins, J.D., Unterberg, E.A., Barton, J.L., Stangeby, P.C.

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