UO2-containing beryllium silicate glass, and radioactive waste liquid treatment method

[0037] The beryllium silicate glass of the present invention comprises the following components represented by mass percent:

[0038] a)SiO2 2 :45

[0039] b) BeO: 16

[0040] c)Na 2 O: 11

[0041] d)Al 2 o 3 :5

[0042] e) oxides of at least one transition element: 5;

[0043] f) at least one rare earth element oxide: 5;

[0044] g) UO 2 :5;

[0045] h) HfO 2 :8.

[0047] The beryllium silicate glass of the present invention comprises the following components represented by mass percent:

[0048] a)SiO2 2 :46

[0049] b) BeO: 16

[0050] c)Na 2 O: 11

[0051] d)Al 2 o 3 :5

[0052] e) oxides of at least one transition element, preferably Fe 2 o 3 、Cr 2 o 3 , MnO 2 , TcO 2 , RuO 2 : 4.5;

[0053] f) At least one rare earth element oxide: 5.5;

[0054] g) UO 2 :5;

[0055] h) HfO 2 :7.

[0057] The beryllium silicate glass of the present invention comprises the following components represented by mass percent:

[0058] a)SiO2 2 :45

[0059] b) BeO: 19

[0060] c)Na 2 O: 11

[0061] d)Al 2 o 3 :5

[0062] e) oxides of at least one transition element, preferably Fe 2 o3 、Cr 2 o 3 , MnO 2 , TcO 2 , RuO 2 : 4.5;

[0063] f) At least one rare earth element oxide: 4.5;

[0064] g)UO 2 :4;

[0065] h) HfO 2 :7.

[0066] The invention also discloses a method for treating moderately radioactive radioactive waste liquid, wherein the waste liquid selectively added with roasting aids is roasted to obtain roasted products, and then vitrification aids are added to the roasting In the product, the calcined product and the vitrification aid are melted in a water-cooled crucible to obtain a glass frit, and then the glass frit is cooled, thereby obtaining the above-mentioned beryllium silicate glass.

[0067] Wherein the roasting aid is selected from aluminum ni