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Title: Measurements of the effective diffusion coefficient of dissolved oxygen and oxidation rate of pyrite by dissolved oxygen in compacted sodium bentonite

Journal Article · · Nuclear Technology
OSTI ID:20030427

The redox condition of the near field is expected to affect the performance of engineered barrier systems. In particular, the oxygen initially existing in the pore spaces of compacted bentonites strongly affects the redox condition of the near field. To assess the influence of the oxygen, research was done to assess its transport parameters in the compacted bentonite and consumption process. To understand the diffusion of dissolved oxygen (DO) in compacted bentonite and to predict the effect of the DO, the measurements of the effective diffusion coefficient of DO in compacted sodium bentonite were made by electro-chemistry. As a result, the following relationship between the dry density of compacted sodium bentonite and the effective diffusion coefficient of DO in compacted sodium bentonite was derived: D{sub e} = 3.0 {+-} 0.5 {times} 10{sup {minus}9} exp({minus}3.7 {+-} 0.2 {times} 10{sup -3}p), where D{sub e} is the effective diffusion coefficient (m{sup 2}s{sup -1}) of DO in compacted sodium bentonite and p is the dry density (kg m{sup -3})of compacted sodium bentonite. The oxygen concentration in the bentonite is expected to be controlled by the oxidation of pyrite as an impurity in the bentonite. To investigate this idea, the rates of pyrite oxidation by DO in compacted sodium bentonite were estimated from the experimental data in pyrite-bentonite systems using the obtained effective diffusion coefficient of DO. The results show that the average of the rate constants of pyrite oxidation by DO in compacted sodium bentonite was 1.16 {+-} 0.35 {times} 10{sup {minus}8}m s{sup {minus}1}, whereas the rate constant in a carbonate-buffered solution (pH = 9.24) was 1.46 {+-} 0.09 {times}10{sup {minus}9}m s{sup {minus}1}.

Research Organization:
Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (JP)
OSTI ID:
20030427
Journal Information:
Nuclear Technology, Vol. 130, Issue 2; Other Information: PBD: May 2000; ISSN 0029-5450
Country of Publication:
United States
Language:
English