Scientific Basis for Nuclear Waste Management XV: Volume 257Claude G. Sombret The MRS Symposium Proceeding series is an internationally recognised reference suitable for researchers and practitioners. |
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Page 355
... dissolved greatly exceeded the fractional amount of U that dissolved , and almost all of the " Cs that dissolved during one week dissolved during the first 6 to 8 hours . Therefore , the gap inventory fraction of Cs was taken to be the ...
... dissolved greatly exceeded the fractional amount of U that dissolved , and almost all of the " Cs that dissolved during one week dissolved during the first 6 to 8 hours . Therefore , the gap inventory fraction of Cs was taken to be the ...
Page 358
... dissolved during the grain - boundary inventory measurement was less than the fractional amount of U that dissolved ) . However , the other Tc and Sr results for that fuel ( 7.4 % FGR ) also appear out of line with the other fuels ...
... dissolved during the grain - boundary inventory measurement was less than the fractional amount of U that dissolved ) . However , the other Tc and Sr results for that fuel ( 7.4 % FGR ) also appear out of line with the other fuels ...
Page 359
... dissolved Cs by subtracting the 0.13 % dissolved the first day ( the amount attributed to Cs from the gap ) and also by subtracting the dissolved U fraction ( equal to the fraction of Cs dissolved congruently with the U from the UO ...
... dissolved Cs by subtracting the 0.13 % dissolved the first day ( the amount attributed to Cs from the gap ) and also by subtracting the dissolved U fraction ( equal to the fraction of Cs dissolved congruently with the U from the UO ...
Contents
IS GEOLOGICAL DISPOSAL THE ONLY ANSWER? | 3 |
BACKFILL MODIFICATION USING GEOCHEMICAL PRINCIPLES | 13 |
RADIOLOGICAL PROTECTION CRITERIA FOR SOLID WASTE | 25 |
Copyright | |
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1992 Materials Research acid actinide alteration americium analysis aqueous backfill Basis for Nuclear bentonite borehole brine buffer calcite calculated canister carbon cations ceramic chemical clay coffinite colloids complex composition concentration containing corrosion rate diffusion coefficient disposal dissolution rate dissolved effects elements energy experimental experiments Figure fission products flow formation fracture geological glass corrosion glass surface granite groundwater ions Koongarra Laboratory layer leach rates leachate Materials Research Society matrix measured minerals noble metals Nuclear Waste Nuclear Waste Management nuclides observed obtained oxidation oxygen parameters particles perovskite phase plutonium porosity potential precipitation Proc pyrochlore R7T7 glass radioactive waste radionuclides ratio reaction redox release Report repository rock SA/V samples saturation shows silica simulated smectite solid solubility solution sorption species specimens Symp Synroc Table temperature tests tracer transport UO₂ uraninite uranium uranyl values Waste Management Yucca Mountain zirconolite zone