An Introduction to Nuclear Waste Immobilisation

Vitrification involves melting of waste materials with glass-forming additives so that the final vitreous product incorporates the waste contaminants in its macro-and micro-structure. Hazardous waste constituents are immobilised either by direct incorporation into the glass structure or by encapsulation. In the first case, waste constituents are dissolved in the glass melt, some being included into the glass network on cooling while others are confined as modifiers. Nuclear waste glasses are not completely homogeneous vitreous materials but contain significant proportions of bubbles, foreign inclusions such as refractory oxides and other immiscible components (Fig. 17.2).
Immobilisation by encapsulation is applied to elements and compounds with a reduced solubility which cannot fit into the glass network. The solubility limits of elements as oxides in silicate glasses are given in Table 17.1.
| Element | Solubility limit (wt.%) |
|---|---|
| Al, Si, P, Pb | >25 |
| Li, B, Na, Mg, K, Ca, Fe, Zn, Rb, Sr, Cs, Ba, Fr, Ra, U | 15 25 |
| Ti, Cu, F, La, Ce, Pr, Nd, Gd, Th, Bi, Zr, Pu, Th | 5 15 |
| Mn, Cr, Co, Ni, Mo | 3 5 |
| C, S, Cl, As, Se, Tc, Sn, Sb, Te, Np | 1 3 |
| H, He, N, Ne, Ar, Br, Kr, Ru, Rh, Pd, Ag, I, Xe, Pt, Au, Hg, Rn | Less than 0.1 |