Np. Laverov et al., MINERALOGY AND GEOCHEMISTRY OF MATRICES FOR THE IMMOBILIZATION OF HIGH-LEVEL RADIOACTIVE-WASTES, Geology of ore deposits, 39(3), 1997, pp. 179-193
According to the IAEA requirements, the liquid high-level radioactive
wastes (HLW) of weapon plutonium production and spent nuclear fuel rep
rocessing are to be transformed to a solid form. For this purpose, alu
mophosphate glass is used in Russia, and borosilicate glass is used in
all other countries. The highly efficient technology of HLW incorpora
tion into glasses is available due to the low melting temperature of t
hese glasses, minimizing radionuclide volatilization and power consump
tion. These glasses are rather highly soluble in aqueous solutions and
tend to recrystallize. The immobilization of actinide-bearing wastes
requires safer matrices providing isolation of the waste for many thou
sands of years. The crystalline matrices where radionuclides are bound
in crystal lattices are the best candidates in this respect. This pap
er contains a review of published data on borosilicate glasses and cov
ers the results of the study of alumophosphate glasses performed at IG
EM RAS. The Synroc ceramics synthesized from the same starting materia
l by the hot pressing technique in Australia and by inductive melting
in a cold crucible in SIA Radon were compared. The latter ceramic mate
rials are composed of mineral grains with larger sizes, include pores
(up to 5 vol %), are free of metal alloys, and do contain molybdates o
f alkali or alkali earth elements. The formation of molybdates is caus
ed by higher oxic conditions of synthesis. When interacting with aqueo
us solutions, the melted ceramics confine actinides securely and Cs an
d Sr poorly due to the high solubility of molybdates. Zirconolite cera
mics with high concentrations of elements simulating radionuclides wer
e also produced and investigated. The distribution of different elemen
ts among the phases of ceramics was studied in detail. It was conclude
d that the melted zirconolite materials are suitable for conservation
of the actinide portion of HLW after its fractionation. The fractionat
ion technology is being promoted now at the radiochemical plant of the
Mayak Production Association (PA Mayak) (Glagolenko et al., 1996; Dze
kun et al., 1996).