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- W122111436 abstract "Dissolution rates were measured on crushed unirradiated UO 2 fuel pellet samples under oxidizing conditions using a flow-through testing method. Water compositions included Nevada Test Site J-13 well water, deionized distilled water (DIW), and variations on the J-13 water composition selected to measure the effects of various J-13 water components on UO 2 dissolution rates. Lower apparent UO 2 dissolution rates were measured in waters containing Si and Ca than in DIW or in dilute NaHCO 3 solution. A thin (approx. 5 nm) U-Si-O surface alteration layer was identified by Auger microprobe examination of UO 2 particles tested at 25°C in Ca-Si containing waters, and a thin layer containing Ca + Si was identified on the surface of particles tested at 85°C. Limited data suggest that the alteration layers act as kinetic barriers to UO 2 dissolution rather than as solubility limiting phases. These experiments and their preliminary results are discussed as they apply to the potential disposal of spent nuclear fuel at the candidate Yucca Mountain repository site." @default.
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- W122111436 date "1990-10-01" @default.
- W122111436 modified "2023-09-24" @default.
- W122111436 title "Effects of water composition on the dissolution rate of UO {sub 2} under oxidizing conditions" @default.
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