Retention capability of cement barriers applied in nuclear field
The fraction released of radioactive cesium from waste forms (obtained by incorporating a given amount of simulated labelled waste materials into cement) was greater than that released when introducing the same amount of waste into a preformed cement container. Moreover, improving cement containers using chemical treatment or additives (organic or inorganic) lowers the fraction released. The effect of waste materials on cement hydration and on the properties of the obtained products has been studied. To improve repository performance it is therefore preferable to ameliorate the confinement properties of preformed cement containers rather than radioactive waste forms. In improving waste forms we are dealing with a complicated system resulting from the interaction of waste materials with cement besides allowing extra doses to workers and finally increasing the final total coasts.
- OSTI ID:
- 47883
- Report Number(s):
- CONF-931108--Vol.333
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of the retention capability of backfill materials in the presence of cement waste form
Water corrosion and release mechanism of cement matrix incorporating simulated medium-level waste