Method of vitrifying high-level radioactive liquid waste

Details Method of vitrifying high-level radioactive liquid waste Method of vitrifying high-level radioactive liquid waste

1995-08-30

1996-06-25

Mai, Ngoclan

Hazardous or toxic waste destruction or containment

Destruction or containment of radioactive waste

By fixation in stable solid media

501152, 501155, 976DIG385, G21F 900

Patent

active

055301746

ABSTRACT:
A method of vitrifying a high-level radioactive liquid waste comprising removing a precipitate composed mainly of Mo and Zr from the high-level liquid waste, mixing the resulting high-level liquid waste with a raw glass material having a chemical composition wherein the B.sub.2 O.sub.3 /SiO.sub.2, ZnO/Li.sub.2 O and Al.sub.2 O.sub.3 /Li.sub.2 O ratios are at least 0.41, at least 1.00 and at least 2.58, respectively, and melt-solidifying the mixture to thereby form a vitrified waste. By using such a raw glass material, there can be obtained a vitrifled waste having the waste content of about 45% by oxide weight in which the same leaching rate as that of a conventional vitrified waste having the waste content of 25% by oxide weight is ensured without suffering from yellow phase separation.

REFERENCES:
patent: 4097401 (1978-06-01), Guber et al.
patent: 4209421 (1980-06-01), Heimerl et al.
patent: 4464294 (1984-08-01), Thiele
patent: 4772431 (1988-09-01), Aubert
patent: 4797232 (1989-01-01), Aubert
Sasage et al., "M15 Phase Separation in Highly Waste Loaded Glass", Preliminary Report of 1994 Fall Meeting of The Atomic Energy Society of Japan (Sep. 28-30, 1994), Published Sep. 5, 1994.

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