P-11.1 Carbon-Based Materials Investigation For ITER Divertor Plates
by T.A. Burtseva, I.V. Mazul, G.L. Saksagansky

P-11.2 The Development of Graphite Materials with the Aim of Reducing Tritium Trapping and the Study of Hydrogen Isotope Retention
by T. A. Burtseva, A. E. Gorodetsky, A. P. Zakharov, A. V. Markin, N. N. Shipkov

P-11.3 Development of Lithium Deposition Techniques for TFTR
by H. W. Kugel, J. Gorman, D. Johnson, G. Labik, G. Lemunyan, D. Mansfield, M. Vocaturo

P-11.4 DOLLOP (Deposition Of Lithium By Laser Outside Of Plasma)
by G. Labik, D. Johnson, G. L, D. Long, D. Mansfield, M. Vocaturo

P-11.5 Ablation Measurement Technique For Fusion Reactor Components
by K. B. Nornoo and T. L. King

P-11.6 Beryllium Plasma Interaction Measurements in PISCES-B
by R. Doerner, A. Grossman, S. C. Luckhardt, R. Serayderian, F. C. Sze,D. G. Whyte

P-11.7 Hydrogen Isotope Retention in B4C Coatings on RGT Graphite After Exposure to High Heat Fluxes in the DIII-D Divertor Plasma
by I. V. Opimach and O. I. Buzhinskij

P-11.8 An Investigation of Beryllium After Deuterium Plasma Bombardment
by M. I. Guseva, V. M. Gureev, L. S. Danelian, V. S. Kulikauskas, V. E. Neumoin, Y. Hirooka, J. Won, D. Sze, R. Boivin

P-11.9 Deuterium Retention in RG-Ti and Poco AXF-5Q Graphites Exposed to High Flux D-Plasma at 1040 and 1400 K
by I. I. Arkhipov, A. E. Gorodetsky, A. P. Zakharov, T. A. Burtseva, B. I. Khripunov, V. V. Shapkin, V. B. Petrov

P-11.10 Plasma-Sprayed Coatings for Plasma-Facing Components
by W. Mallener, K. H. Rauwald, D. Stover

P-11.11 Deuterium and Tritium Permeability through First Wall Materials
by Yu.N. Zouev, Yu.N. Dolinsky, I.A. Lyasota, N.N. Markelov, Yu.L. Reprinzev, A.E. Shestakov

P-11.12 Tritium Recovery from the TFTR Vessel
by A. Nagy, E. Amerescu, W. Blanchard, R. Camp, M. Casey, K. Chase, M. Cropper, T. Czeizinger, M. DiMattia, C. Gentile, J. Gething, M. Gibson, J. Langford, J. Hosea, D. Hyatt, M. Kalish, J. Kamperschroer, S. Langish, D. Miller, D. Mueller, G. Pearson, S.Raftopoulos, R. Raucci, T. Stevenson, A. vonHalle, J. Winston

P-11.13 Tritium Removal by CO₂ Laser Heating
by C. H. Skinner, D. Mueller, B. L. Doyle, W. Wampler

P-11.14 A Simplified Torus Module for use within an Integrated Dynamic Fusion Fuel Cycle Tritium Model for ITER
by W. Kuan and G. Federici, P. Gierszewski

P-11.15 Development of plasma facing components for ITER in Efremov Institute
by V.A.Belyakov, O.G.Filatov, I.V.Mazul