Scientific Basis for Nuclear Waste Management XIX: Volume 412Safe 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 book, the nineteenth 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: excess plutonium dispositioning; spent nuclear fuel; glass waste forms; ceramic and crystalline waste forms; cement waste forms; waste processing; waste container materials; speciation and sorption; bentonite barriers; flow and transport; repository site characterization; natural analogs and performance assessment. |
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Page 873
... TECHNETIUM IN A GEOLOGICAL DISPOSAL VAULT FOR USED NUCLEAR FUEL - RAMIFICATIONS OF A RECENT DETERMINATION OF THE ENTHALPY OF FORMATION OF TcO2 ( cr ) R.J. LEMIRE * , D.J. JOBE ** * AECL , Chalk River Laboratories , Chalk River , ON KOJ ...
... TECHNETIUM IN A GEOLOGICAL DISPOSAL VAULT FOR USED NUCLEAR FUEL - RAMIFICATIONS OF A RECENT DETERMINATION OF THE ENTHALPY OF FORMATION OF TcO2 ( cr ) R.J. LEMIRE * , D.J. JOBE ** * AECL , Chalk River Laboratories , Chalk River , ON KOJ ...
Page 878
... technetium species at saturation as a function of Ez for Case 2. The solid in the experiments used to obtain the database 4G ° values for the reduced technetium species was assumed to be an amorphous oxide less stable than TcO2 ( cr ) ...
... technetium species at saturation as a function of Ez for Case 2. The solid in the experiments used to obtain the database 4G ° values for the reduced technetium species was assumed to be an amorphous oxide less stable than TcO2 ( cr ) ...
Page 879
... technetium solution species would be higher than for Cases 1 and 2. This assumes the reported measurements of the standard TcO2 ( s ) / TcO¡ ( aq ) potentials are in error ( perhaps due to radiolysis effects ) , or that at least the ...
... technetium solution species would be higher than for Cases 1 and 2. This assumes the reported measurements of the standard TcO2 ( s ) / TcO¡ ( aq ) potentials are in error ( perhaps due to radiolysis effects ) , or that at least the ...
Contents
Options and Choices in the Disposition | 3 |
Plutonium Incineration in LWRS by a OnceThrough | 15 |
Performance Assessment of Zircon as | 25 |
Copyright | |
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Common terms and phrases
actinides aeschynite analysis aqueous backfill Basis for Nuclear bentonite blend Boom clay calculated cations cement ceramic chemical clay clinoptilolite coefficient components composition concentration containing corrosion rate crystals decrease density diffraction diffusion disposal dissolution dissolved distribution effect electron elements euxenite experimental exposure Figure fraction fracture groundwater hydration increase initial layer leach rates magnetite material matrix measured melting metal minerals National Laboratory Nuclear Waste Nuclear Waste Management nuclide observed oxide parameters particles perovskite phase plutonium porosity potential precipitation predicted Proc pyrochlore R.C. Ewing Radioactive Waste radionuclides ratio reaction redox release repository rock samples saturation schoepite Scientific Basis silica simulated SiO2 smectite solid solubility solution sorption species specimens structure surface Synroc Table technetium temperature tests transport tuff uranium values vitrification waste form waste glass Waste Management waste package Yucca Mountain zircon zirconia zirconolite zone ZrO2