scholarly journals STORAGE OF LIQUID RADIOACTIVE WASTES AT THE SAVANNAH RIVER PLANT.

1969 ◽  
Author(s):  
R. M. Girdler
Author(s):  
R. M. WALLACE ◽  
W. H. HALE ◽  
R. F. BRADLEY ◽  
H. L. HULL ◽  
J. A. KELLEY ◽  
...  

1985 ◽  
Vol 58 (4) ◽  
pp. 315-317 ◽  
Author(s):  
V. A. Kichik ◽  
G. A. Yagodin ◽  
N. F. Kuleshov ◽  
A. A. Svittsov

1966 ◽  
Vol 20 (3) ◽  
pp. 314-316
Author(s):  
V. G. Vereskunov ◽  
K. P. Zakharova ◽  
V. V. Kulichenko ◽  
P. V. Zimakov

Atomic Energy ◽  
2006 ◽  
Vol 100 (2) ◽  
pp. 83-89 ◽  
Author(s):  
I. M. Kosareva ◽  
M. K. Savushkina ◽  
S. A. Kabakchi ◽  
S. V. Korotkevich ◽  
V. M. Kudryavtsev

1984 ◽  
Vol 44 ◽  
Author(s):  
Christine A. Langton

AbstractA cement-based waste form, “saltstone,” has been designed for disposal of Savannah River Plant low-level radioactive salt waste. Laboratory and field tests indicate that this stabilization process greatly reduces the mobility of all of the waste constituents in the surface and near-surface environment. Bulk properties of this material have been tailored with respect to salt leach rate, permeability, and compressive strength. Microstructure and mineralogy were characterized by SEM and x-ray diffraction analyses.Compressive strength was found to increase as the water to cement ratio decreased. Porosity and mean pore size increased with increasing water to cement ratios. Bulk diffusivities of the various ions dissolved in the pore solutions were also found to increase as water to cement ratios increased.


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