Scientific basis for nuclear waste management XXIV: symposium held August 27-31, 2000, Sydney, Australia
Kaye P. Hart, Gregory R. Lumpkin
Materials Research Society, 2001 - Technology & Engineering - 1232 pages
Safe and effective management of nuclear waste provides a broad range of challenges for materials science. Waste processing, waste form and engineered barrier properties, interactions between engineered and geological systems, radiation effects, chemistry and transport of waste species, and long-term predictions of repository performance are just some of the scientific problems facing modern society. This volume, the 24th in a very successful series from MRS, offers an international and interdisciplinary perspective on the issues, and features developments in both fundamental and applied areas. Topics include: conditioning of wastes; immobilization of wastes in cement and bitumen; glass waste forms; ceramic waste forms; spent fuel; canisters; engineered barriers; microbiology and thermodynamics; repository studies; natural systems; and solubility, transport modeling and migration.
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2001 Materials Research actinides alloy alteration assessment Basis for Nuclear behavior bentonite Boom Clay brannerite buffer calculated canister carbon cations cement cenospheres ceramics cesium chemical coefficient composition concentration containing corrosion crystalline crystals decrease diffusion dissolution rate dose dry density effect electron evolution experimental experiments Figure fraction fracture fuel matrix geological disposal glass glass-ceramics groundwater hollandite hydrogen increase initial ions irradiation layer leach rate Materials Research Society measured microbial minerals montmorillonite neodymium nuclear fuel Nuclear Waste Nuclear Waste Management nuclides oxidation oxygen parameters performance permeability perovskite phase plutonium pore water porosity potential precipitation Proc pyrochlore radioactive waste radiolysis radionuclides ratio reaction redox repository rock rutile safety samples saturation scenarios silica simulated smectite sodalite solubility solution sorption specimens spent fuel surface Symp Synroc Table temperature uranium values waste form Waste Management zeolite zirconolite zone