Calculated uranium solubility in groundwater: implications for nuclear fuel waste disposal

1982 ◽  
Vol 60 (13) ◽  
pp. 1759-1766 ◽  
Author(s):  
Bruce Goodwin

Uranium solubilities of the order of 10−10 M have been calculated for a range of conditions which are considered to be representative of those expected in a Canadian nuclear fuel waste disposal vault. Factors taken into consideration include the pH and Eh range expected for deep groundwaters, the projected temperature range near a nuclear fuel waste disposal vault, the effect of the composition of two representative groundwaters, the effect of non-ideality, and the effect of the stability of several uranium solids.The model used in these calculations is based on the assumption of chemical equilibrium. Calculations show that the most important factors influencing uranium solubility under the postulated conditions are pH and Eh.These results applied to an assessment of the nuclear fuel waste disposal program suggest that uranium concentrations will be very low in the disposal vault, and that the irradiated UO2 fuel matrix will remain relatively intact for long periods of time.

1996 ◽  
Vol 42 (4) ◽  
pp. 401-409 ◽  
Author(s):  
M. Gascoyne

The concept for disposal of Canada's nuclear fuel waste in a geologic environment on the Canadian Shield has recently been presented by Atomic Energy of Canada Limited (AECL) to governments, scientists, and the public, for review. An important part of this concept concerns the geochemical environment of a disposal vault and includes consideration of rock and groundwater compositions, geochemical interactions between rocks, groundwaters, and emplaced vault materials, and the influences and significance of anthropogenic and microbiological effects following closure of the vault. This paper summarizes the disposal concept and examines aspects of the geochemical environment. The presence of saline groundwaters and reducing conditions at proposed vault depths (500–1000 m) in the Canadian Shield has an important bearing on the stability of the used nuclear fuel, its container, and buffer and backfill materials. The potential for introduction of anthropogenic contaminants and microbes during site investigations and vault excavation, operation, and sealing is described with examples from AECL's research areas on the Shield and in their underground research laboratory in southeastern Manitoba. Keywords: nuclear waste disposal, geochemistry, Canadian Shield, groundwater chemistry.


1981 ◽  
Vol 6 ◽  
Author(s):  
Donald J. Cameron

ABSTRACTNuclear fuel waste disposal research in Canada is concentrating on hard-rock disposal. The research programs concerned with the man-made components of the disposal system are reviewed. Irradiated fuel and solidified reprocessing wastes are both being researched, as are durable containers, and buffer and backfill materials. This review concentrates mainly on the more scientific aspects of the research, which contribute to the selection of preferred options for the various components of the system, and which support directly or indirectly the safety analysis of the disposal concept. Some technology development is included in the program now, and this is expected to expand as confidence in the acceptability of the disposal concept grows.


1993 ◽  
Vol 13 (2) ◽  
pp. 153-170 ◽  
Author(s):  
G.A. Bird ◽  
M. Stephenson ◽  
R.J. Cornett

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