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Beryllium silicate glass containing Pr2O3 and method for treating radioactive waste liquid

A technology of beryllium silicate and pr2o3, which is applied in the fields of radioactive purification and nuclear engineering, can solve the problems of affecting the life expectancy of materials, low mechanical strength, and easy fire, etc., to achieve enhanced stability and corrosion resistance, enhanced stability and Corrosion resistance, effect of enhancing mechanical strength

Inactive Publication Date: 2014-03-19
溧阳市浙大产学研服务中心有限公司
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, bituminous treatment has several major disadvantages: reduced stability, easy fire, limited range of use, low mechanical strength
However, cement curing has two significant disadvantages: the volume of the waste material doubles after coating; it affects the life expectancy of the obtained material
However, the stability, mechanical strength and corrosion resistance of borosilicate glass still cannot meet the needs of people to seal moderately radioactive waste liquid.

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[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) Pr 2 o 3 :5;

[0044] g) at least one actinide oxide, such as UO 2 , ThO 2 、Am 2 o 3 , PuO 2 , CmO 2 , NpO 2 :5;

[0045] h) HfO 2 :8.

Embodiment 2

[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) Pr 2 o 3 : 5.5;

[0054] g) at least one actinide oxide, such as UO 2 , ThO 2 、Am 2 o 3 , PuO 2 , CmO2 , NpO 2 :5;

[0055] h) HfO 2 :7.

Embodiment 3

[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 o 3 、Cr 2 o 3 , MnO 2 , TcO 2 , RuO 2 : 3.5;

[0063] f) Pr 2 o 3 : 4.5;

[0064] g)UO 2 :5;

[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 nitrate, iron nitrate, ...

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PUM

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Abstract

The invention discloses beryllium silicate glass comprising the following components by the mass percentage: a) 42-49% of SiO2; b) 15-20% of BeO; c) 11-14% of Na2O; d) 5-10% of Al2O3; e) 3-6.5% of at least one transition element oxide; f) 3-6.5% of Pr2O3; g) 3-6.5% of at least one actinide element oxide, such as UO2, ThO2, Am2O3, PuO2, CmO2 and NpO2; and h), 5-8% of HfO2. The glass has extremely high stability, extremely excellent mechanical strength and extremely high chemical corrosion resistance ability on radiation; and the glass can quite well seal, preserve and isolate a waste liquid under a volume shrinking condition.

Description

technical field [0001] The invention relates to a beryllium silicate glass used for sealing, preserving and isolating radioactive waste liquid in nuclear reactor devices. Background technique [0002] Moderately radioactive radioactive waste water is produced in nuclear fuel regeneration equipment such as nuclear reactors, and is currently mainly treated by asphalting or cement solidification. However, the use of asphalt treatment has several major disadvantages: reduced stability, easy fire, limited range of use, and low mechanical strength. The cost of cement treatment is moderate, the application is simple, the mechanical strength is good, and the stability is long-lasting. But cement curing has two significant disadvantages: the volume of the waste material doubles after coating; and it affects the life expectancy of the obtained material. [0003] In addition, people are now also studying the use of glass to seal radioactive waste liquid. Because of its amorphous stat...

Claims

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Application Information

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IPC IPC(8): C03C3/095G21F9/16G21F9/22
Inventor 梅欣
Owner 溧阳市浙大产学研服务中心有限公司
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