Glass solidified body synergistically solidifying SrF2 and high-sodium high-iron waste and preparation method thereof

A solidification method, vitrification technology, applied in radioactive purification, nuclear engineering, etc., can solve the problems of low waste containment capacity, complicated preparation process of solidified body, poor thermal stability, etc., to improve solid waste treatment capacity, improve chemical and The effect of thermal stability

Active Publication Date: 2020-11-10
JINGDEZHEN CERAMIC INSTITUTE
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0007] In order to solve the SrF existing in the prior art 2 solid waste especially 90 SrF 2 The radioactive waste vitrified body has poor thermal stability, low waste containment capacity, complex preparation process of the solidified body, no energy saving, and easy to caus

Method used

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  • Glass solidified body synergistically solidifying SrF2 and high-sodium high-iron waste and preparation method thereof
  • Glass solidified body synergistically solidifying SrF2 and high-sodium high-iron waste and preparation method thereof
  • Glass solidified body synergistically solidifying SrF2 and high-sodium high-iron waste and preparation method thereof

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1～3

[0055] Preparation examples 1-3 glass solidified body adopts the same raw material, namely SrF 2 Simulated high-level radioactive waste, No. 1 high-sodium and high-iron content simulated high-level radioactive waste, Fe 2 o 3 and P 2 o 5 . Among them, the raw material for preparing No. 1 high-sodium and high-iron content simulated high-level radioactive waste is Na 2 CO 3 , NaF, Na 2 SO 3 , CeO 2 、Nd 2 o 3 、 Bi 2 o 3 、Al 2 o 3 , SiO 2 , MnO 2 , PbO 2 and ZrO 2 . Taking the preparation of 100 g of simulated waste vitrified bodies as an example, the detailed raw material ratios for preparing the vitrified bodies of Examples 1-3 are as follows. Embodiment 1 Vitrified body: 18.2663gSrF 2 , 5.5785gNa 2 CO 3 、63.1269gP 2 o 5 , 11.5977gFe 2 o 3 , 0.1096gNaF, 0.0183gNa 2 SO 3 , 0.2740gCeO 2 , 0.3899gNd 2 o 3 , 0.4059gBi 2 o 3 , 0.0812gAl 2 o 3 , 0.0478gSiO 2 , 0.0319gMnO 2 , 0.0522gPbO 2 , 0.0108gNiO, 0.0089gZrO 2 . Embodiment 2 Vitrified body: ...

Embodiment 4

[0057] The raw material used in embodiment 4 is SrF 2 Simulated high-level radioactive waste, No. 2 high-sodium and high-iron content simulated high-level radioactive waste, Fe 2 o 3 and P 2 o 5 . Among them, the raw material for preparing No. 2 high-sodium and high-iron content simulated high-level radioactive waste is Na 2 CO 3 、MoO 3 , La 2 o 3 , Fe 2 o 3 , SrCO 3 , MnO 2 and TeO 2 . According to the formula of Example 4, the mass of each raw material needed to prepare 100 g of the glass solidified body of Example 4 was calculated. Accurately weigh 32.2gSrF with a balance 2 , 7.7gNa 2 CO 3 , 11.7gFe 2 o 3 , 42.6gP 2 o 5 , 1.4gMoO 3 , 3.1gLa 2 o 3 , 0.8gSrCO 3 , 0.2gMnO 2 and 0.2gTeO 2 , mix the raw materials uniformly to obtain the vitrified body mixture, and then put it into a corundum crucible and place it in a high-temperature furnace. Slowly raise the temperature from room temperature to 450°C, after holding at 450°C for 2 hours, quickly rais...

Embodiment 5

[0059] The raw material used in embodiment 5 is SrF 2 Simulated high-level radioactive waste, No. 3 high-sodium and high-iron content simulated high-level radioactive waste, Na 2 CO 3 , Fe 2 o 3 and P 2 o 5 . Fe 2 o 3 、Na 2 CO 3 , MnO 2 、Al 2 o 3 , NiO, CaCO 3 , La 2o 3 , SiO 2 , SrCO 3 , Li 2 CO 3 . According to the formula of Example 5, calculate the mass of each raw material needed to prepare 100 g of the glass solidified body of Example 5. Accurately weigh 28.7gSrF with a balance 2 , 8.1gNa 2 CO 3 , 12.2gFe 2 o 3 , 44.9gP 2 o 5 , 1.9gMnO 2 , 1.3gAl 2 o 3 , 0.9NiO, 0.9CaCO 3 , 0.6gLa 2 o 3 , 0.2SiO2 2 , 0.2gSrCO 3 , 0.1gLi 2 CO 3 , mix the raw materials uniformly to obtain the vitrified body mixture, and then put it into a corundum crucible and place it in a high-temperature furnace. Slowly raise the temperature from room temperature to 450°C and keep it at 450°C for 2 hours, then quickly raise the temperature from 450°C to 800°C at a h...

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Abstract

The invention belongs to the technical field of solid waste treatment, and particularly relates to a synergistic solidifying method for SrF2 solid waste and high-sodium high-iron solid waste. The method includes mixing SrF2 solid waste and high-sodium high-iron solid waste, melting, forming and annealing to obtain a glass solidified body. In the high-sodium high-iron solid waste, the sum of mole percentages of the Na2O and Fe2O3 components is in the range of 58-79 mol%. The invention provides an innovative idea of combined treatment of the SrF2 solid waste and the high-sodium high-iron solid waste for the first time, and finds that the combined treatment of the SrF2 solid waste and the high-sodium high-iron solid waste can generate a synergistic effect, the solid waste treatment capacity can be improved, the chemical and thermal stability of the glass solidified body can be improved, and in addition, F can be synchronously solidified. According to the technical scheme, waste is treatedwith waste, and in addition, unexpected effects of improving the chemical and thermal stability of a solidified body, achieving F synchronous curing which is difficult to achieve in the industry andthe like can be achieved synergistically. The technical scheme provided by the invention can be applied to combined treatment of SrF2 and high-sodium high-iron radioactive solid waste.

Description

technical field [0001] The invention belongs to the technical field of waste treatment and relates to safe solidification and disposal of high-level radioactive waste. The invention also belongs to the field of new material inventions, and relates to the preparation of a phosphate glass with high chemical stability and high thermal stability. Background technique [0002] 90 Sr is nuclear fuel 235 The main fission product of U, the yield is 5.9%, and strontium waste accounts for a large proportion of nuclear power waste. 90 Sr, as a by-product of the nuclear fuel reprocessing plant, is separated from the high-level radioactive waste liquid that recovers U and Pu, and its main form is 90 SrF 2 . Cured with industrial borosilicate glass 90 SrF 2 High-level radioactive waste has the following problems: (1) 90 SrF 2 Waste is easy to cause phase separation of borosilicate glass, and it is necessary to drastically reduce the waste inclusion capacity in the vitrified body ...

Claims

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Application Information

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IPC IPC(8): G21F9/34G21F9/28
CPCG21F9/28G21F9/34
Inventor 李秀英肖卓豪陶歆月杨柯罗民华汪永清
Owner JINGDEZHEN CERAMIC INSTITUTE
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