Improved cement container applied in nuclear field
- Malaeb El-Gamaa, Giza (Egypt)
The effect of waste materials and additives, on the hydration of cement and on the properties of the obtained products, has been studied using X-ray diffraction, IR-analyses, thermal reaction and weight loss, porosity and pore parameters, rate of release, retardation and diffusion coefficients. The results obtained from x-ray diffraction show that treatment of cement containers by inorganic additives has no or a very slight effect on the hydration of cement compared with the noticeable retardation of hydration caused by the presence of borate in cement borate-waste forms. These results were further illustrated by the obtained thermochemical data and IR-analyses. The fraction released of radionuclides from waste forms obtained by incorporating a given amount of simulated labelled waste materials into cement was considerably higher than that released when introducing the same amount of waste into a preformed cement container. Improving cement containers using chemical treatment or additives has further lowered the fraction released remarkably. Both apparent and intrinsic diffusion coefficients were determined and used to calculate the rate of release of cesium radionuclide from waste materials introduced in containers having different thickness. The calculated and the experimentally determined values were in good agreement.
- OSTI ID:
- 469729
- Report Number(s):
- CONF-960804--Vol.1
- Country of Publication:
- United States
- Language:
- English
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