Desorption kinetics of radionuclides fixed in cement matrix

Journal Article · Tue Nov 30 23:00:00 EST 1993 · Nuclear Technology; (United States)

OSTI ID:5746028

Krishnamoorthy, T M; Joshi, S N; Doshi, G R; Nair, R N ^[1]

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1. Bhabha Atomic Research Centre, Bombay (India). Health Physics Div.

Leach characteristics of some typical nuclides such as cesium, strontium, cobalt, I[sup [minus]], and CO[sup [minus]2][sub 3] from ordinary portland cement waste forms have been studied using the ISO test method and radiotracers of the respective nuclides, i.e., [sup 134]Cs, [sup 85]Sr, [sup 60]Co, [sup 131]I, and [sup 14]C. The leach studies suggest a rapid release of radioactivity in the beginning (fast component) followed by slow release for long periods of time (slow component). A mathematical model has been simulated to describe the leaching kinetics of these nuclides from the cement matrix. The effective diffusion coefficient D[sub [ell]] is computed from the two componental diffusion coefficients, and the retardation factor ([alpha]) for a nuclide is evaluated from a knowledge of the radioactivity distribution in the aqueous and solid phase at equilibrium. The product [alpha]D[sub [ell]] for all the nuclides studied has been found to be approximately constant and is equal to the intrinsic diffusion coefficient in the cement matrix. The net fractional release of different radionuclides from cement waste form showed a decreasing pattern, i.e., [sup 134]Cs > [sup 131]I > [sup 85]Sr > [sup 14]Cr > [sup 60]Co indicating the largest diffusion coefficient for cesium as 10[sup [minus]2] cm[sup 2]/day and the least for [sup 14]C as 3 [times] 10[sup [minus]8] cm[sup 2]/day.

• OSTI ID: 5746028
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 104:3; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

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NUCLEI
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ODD-EVEN NUCLEI
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PORTLAND CEMENT
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
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SEPARATION PROCESSES
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STRONTIUM 85
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UNDERGROUND DISPOSAL
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