Scientific Basis for Nuclear Waste Management XIII: Volume 176Virginia M. Oversby, Paul W. Brown Annotation The symposium, held in Boston, May 1989, placed special emphasis on cementitious materials to encourage participation from researchers in the area of low and intermediate level waste. Sections cover topics in performance, leaching, and durability of cementitious materials; modeling the dissolution of nuclear waste forms; waste glass performance; spent fuel performance; container and fuel cladding performance; sorption, speciation, migration and near field effects; sizing and scaling effects; and performance assessment. Acidic paper. Annotation copyrighted by Book News, Inc., Portland, OR. |
Contents
ENCAPSULATION OF RADIOIODINE IN CEMENTITIOUS WASTE FORMS | 15 |
EFFECT OF CURING TEMPERATURE ON THE PROPERTIES | 23 |
EFFECT OF YRADIATION ON THE MICROSTRUCTURE | 31 |
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1990 Materials Research actinides analcime analysis anionic aqueous backfill Basis for Nuclear bentonite Boom clay borosilicate glass buffer calcium calculated cations cement Ceram cesium chemical clay components composition concentration concrete containing corrosion cracks decrease diffusion coefficient dissolution rate elements enthalpies equation equilibrium experimental experiments Figure formation fracture glass dissolution grain groundwater grout hydration hydraulic conductivity increase initial irradiation ISBN kinetics leachate leaching mass loss Materials Research Society matrix measured migration mineral Nuclear Waste Nuclear Waste Management nuclides observed oxidation parameters performed phase pore porosity precipitation predicted pressure Proc radioactive waste radionuclides ratio reaction redox Report repository rock SA/V samples saturation schoepite silica simulated SiO2 smectite solid solubility solution sorbed sorption species of 60Co specimen spent fuel SRPC surface area Symp Table temperature tests thickness uranium values volume waste forms Waste Management Yucca Mountain