Design and manufacturing status of trim coils for the Wendelstein 7-X stellarator experiment by Riße, K., Rummel, Th, Freundt, S., Dudek, A., Renard, S., Bykov, V., Köppen, M., Langish, S., Neilson, G.H., Brown, Th, Chrzanowski, J., Mardenfeld, M., Malinowski, F., Khodak, A., Zhao, X., Eksaa, G.

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Development of an electrostatic dust detector for use in a tokamak reactor by Bader, A., Skinner, C. H., Roquemore, A. L., Langish, S.

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Studies of tritiated co-deposited layers in TFTR by Skinner, C.H., Gentile, C.A., Ascione, G., Carpe, A., Causey, R.A., Hayashi, T., Hogan, J., Langish, S., Nishi, M., Shu, W.M., Wampler, W.R., Young, K.M.

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Tritium removal from codeposits on carbon tiles by a scanning laser by Skinner, C.H, Gentile, C.A, Carpe, A, Guttadora, G, Langish, S, Young, K.M, Shu, W.M, Nakamura, H

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Inertial Fusion Energy Power Reactor Fuel Recovery System by Gentile, C. A., Kozub, T., Langish, S. W., Ciebiera, L. P., Nobile, A., Wermer, J., Sessions, K.

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Comparison and Evaluation of Various Tritium Decontamination Techniques and Processes by Gentile, C. A., Langish, S. W., Skinner, C. H., Ciebiera, L. P.

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Tritiated Dust Levitation by Beta-Induced Static Charge by Skinner, C. H., Gentile, C. A., Ciebiera, L., Langish, S.

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Detritiation of the JET Carbon Tiles by Flame Heating by Perevezentsev, A., Bell, A., Brennan, D., Miller, A., Healer, A., Gentile, C., Ciebiera, L., Langish, S.

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The effect of oxygen on the release of tritium during baking of TFTR D–T tiles by Shu, W.M, Gentile, C.A, Skinner, C.H, Langish, S, Nishi, M.F

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Tritium Removal by Laser Heating and Its Application to Tokamaks by Skinner, C. H., Gentile, C. A., Guttadora, G., Carpe, A., Langish, S., Young, K. M., Nishi, M., Shu, W.

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Tritium Decontamination of TFTR D-T Plasma Facing Components Using an Ultra Violet Laser by Shu, W. M., Kawakubo, Y., O'hira, S., Oya, Y., Hayashi, T., Nakamura, H., Iwai, Y., Nishi, M. F., Gentile, C. A., Skinner, C. H., Langish, S., Guttadora, G., Carpe, A., Young, K. M.

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Ensuring compliance and consistency in an R&D environment: The PPPL Office of Project Management by Dodson, T., Stevenson, T., Egebo, T., Strykowsky, R., Langish, S., Williams, M.

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Conceptual Design of a Plasma Exhaust and Fuel Recovery System for an Inertial Fusion Energy (IFE) Power Reactor by Gentile, C.A., Langish, S.W., Kozub, T., Priniski, C., Dodson, T., Gettelfinger, G., Paul, B., Ciebiera, L., Wermer, J., Nobile, A., Sessions, K., Sethian, J., Robson, A.E.

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Plasma wall interaction and tritium retention in TFTR by Skinner, C.H., Amarescu, E., Ascione, G., Blanchard, W., Barnes, C.W., Batha, S.H., Beer, M., Bell, M.G., Bell, R., Bitter, M., Bretz, N.L., Budny, R., Bush, C.E., Camp, R., Casey, M., Collins, J., Cropper, M., Chang, Z., Darrow, D.S., Duong, H.H., Durst, R., Efthimion, P.C., Ernst, D., Fisch, N., Fonck, R.J., Fredrickson, E., Fu, G.Y., Furth, H.P., Gibson, M., Gilbert, J., Grisham, L.R., Hammett, G., Hawryluk, R.J., Herrmann, H.W., Hill, K.W., Janos, A., Jassby, D.L., Jobes, F.C., Johnson, D.W., Johnson, L.C., Kamperschroer, J., Kalish, M., Kugel, H., Langford, J., Langish, S., Lamarche, P.H., Levinton, F.M., Machuzak, J., Majeski, R., Manikam, J., Mansfield, D.K., Mazzucato, E., McGuire, K.M., Mika, R., McKee, G., Meade, D.M., Medley, S.S., Mikkelsen, D.R., Mynick, H.E., Mueller, D., Nagy, A., Nazikian, R., Ono, M., Owens, D.K., Park, H., Paul, S.F., Pearson, G., Petrov, M., Phillips, C.K., Raftopoulos, S., Ramsey, A., Raucci, R., Redi, M.H., Rewoldt, G., Rogers, J., Roquemore, A.L., Ruskov, E., Sabbagh, S.A., Schilling, G., Schivell, J.F., Schmidt, G.L., Scott, S.D., Sesnic, S., Strachan, J.D., Stevenson, T., Stotler, D.P., Takahashi, H., Tang, W., Taylor, G., Tighe, W., Timberlake, J.R., von Halle, A., Walters, R.T., White, R.B., Wilson, J.R., Winston, J., Wong, K.L., Young, K.M., Zarnstorff, M.C., Zweben, S.J.

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Plasma wall interaction and tritium retention in TFTR by Skinner, C

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Studies of tritiated co-deposited layers in TFTR by SKINNER, C. H, GENTILE, C. A, WAMPLER, W. R, YOUNG, K. M, ASCIONE, G, CARPE, A, CAUSEY, R. A, HAYASHI, T, HOGAN, J, LANGISH, S, NISHI, M, SHU, W. M

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The development of a hibachi window for electron beam transmission in a KrF laser by Gentile, C.A., Parsells, R., Butler, J.E., Sethian, J.D., Ciebiera, L., Hegeler, F., Jun, C., Langish, S., Myers, M.

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Design improvements and lessons learned for the TFTR Tritium Cleanup and Gas Holding Tank Sampling systems by Kalish, M., LaMarche, P., Viola, M., Anderson, J.L., Ciebiera, L., Rossmassler, R., Walters, R.T., Langish, S., Casey, M.

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Tritium reduction and control in the vacuum vessel during TFTR outage and decommissioning by Blanchard, W., Camp, R., Carnevale, H., Casey, M., Collins, J., Gentile, C.A., Gibson, M., Hosea, J.C., Kalish, M., Langford, J., Langish, S., Miller, D., Nagy, A., Pearson, G.G., Raucci, R., Rule, K., Winston, J.

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Tritium recovery from the TFTR vessel by Nagy, A., Amerescu, E., Blanchard, W., Camp, R., Casey, M., Chase, K., Cropper, M., Czeizinger, T., DiMattia, M., Gentile, C., Gething, J., Gibson, M., Langford, J., Hosea, J., Hyatt, D., Kalish, M., Kamperschroer, J., Langish, S., Miller, D., Mueller, D., Pearson, G., Raftopoulos, S., Raucci, R., Stevenson, T., VonHalle, A., Winston, J.

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