Call Number (LC) Title Results
E 1.99: conf-791112-26 Role of large-scale permeability measurements in fractured rock and their application at Stripa 1
E 1.99: conf-791112-27 Characterization of discontinuities in the Stripa granite 1
E 1.99:conf-791112-28 Control of radionuclide migration in soil by the application of dc electric current 1
E 1.99: conf-791112-29 Perspective of waste isolation research issues and assessment of consequences for radionuclide release 1
E 1.99: conf-791112-30 Corrosion resistant metallic canisters an important element of a multibarrier disposal program. [TiCode-12 (Ti-0. 8% Ni-0. 3% Mo)] 1
E 1.99: conf-791112-31 Mechanism for elevated temperature leaching 1
E 1.99: conf-791112-33 In situ experiments to support development of the waste isolation pilot plant (WIPP) 1
E 1.99: conf-791112--34 Interaction of radionuclides with geomedia from the Nevada Test Site 1
E 1.99: conf-791112-35 Development of an ion-exchange process for removing cesium from high-level radioactive liquid wastes 1
E 1.99: conf-791112-36 Amorphous surface layers in Ti-implanted Fe 1
E 1.99: conf-791112-37 Hydrogen and defects in laser annealed amorphous silicon 1
E 1.99: conf-791112-38 Implantation studies of impurity immobilization mechanisms 1
E 1.99: conf-791112-39 Precipitation in ion-implanted Al during electron beam pulsed annealing 1
E 1.99: conf-791112-41 EPR of ion-implanted, laser-annealed silicon 1
E 1.99: conf-791112-42 Backfill as an engineered barrier for nuclear waste management. [Bentonite-hectorite] 1
E 1.99:conf-791112-43 Vitrification of high-level alumina nuclear waste 1
E 1.99: conf-791112-44 Status report on studies to assess the feasibility of storing nuclear waste in Columbia Plateau basalts 1
E 1.99:conf-791112-45 General criteria for radioactive waste disposal 1
E 1.99: conf-791112-46 Canister compatibility with Carlsbad salt 1
E 1.99: conf-791112-47 Preliminary rate expressions for analysis of radionuclide migration resulting from fluid flow through jointed media 1