Preparation method for high-sulfur, high-sodium and high-level-liquid-waste glass-ceramic solidifier

A technology of high-level radioactive waste liquid and glass ceramics, applied in radioactive purification, nuclear engineering, etc., can solve the problem of yellow phase and achieve the effect of good chemical stability

Active Publication Date: 2019-01-25
SOUTHWEAT UNIV OF SCI & TECH
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

So as to provide an effective way to solve the "yellow phase" problem encountered in borosilicate vitrified high-sulfur, high-sodium and high-level radioactive waste liquid

Method used

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  • Preparation method for high-sulfur, high-sodium and high-level-liquid-waste glass-ceramic solidifier
  • Preparation method for high-sulfur, high-sodium and high-level-liquid-waste glass-ceramic solidifier
  • Preparation method for high-sulfur, high-sodium and high-level-liquid-waste glass-ceramic solidifier

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0032] A method for preparing a high-sulfur, high-sodium, high-level radioactive waste liquid glass-ceramic solidified body, the steps are:

[0033] a. Prepare barite-containing high-sulfur, high-sodium and high-level radioactive waste liquid: add Ba(NO 3 ) 2 solution, control SO 4 2- and Ba 2+ The molar ratio is 1:1, and the high-sulfur, high-sodium and high-level radioactive waste liquid containing barite is obtained;

[0034] b. Ingredients: according to SiO 2 54.0%, B 2 o 3 20.0%, Na 2 O 4.5%, CaO 5.0%, Al 2 o 3 3.5%, MgO1.5%, TiO 2 1.5%, the component composition and mass percentage of 10% of the barite-containing high-sulfur, high-sodium and high-level radioactive waste liquid calculated as waste oxides are taken from each component;

[0035] c. Mixing reaction: After mixing the raw materials, put them in a furnace (for example: muffle furnace or glass melting furnace, etc.) and heat-preserve and calcinate at 850°C for 1h (to decompose the carbonate); then...

Embodiment 2

[0037] A method for preparing a high-sulfur, high-sodium, high-level radioactive waste liquid glass-ceramic solidified body, the steps are:

[0038] a. Prepare barite-containing high-sulfur, high-sodium and high-level radioactive waste liquid: add Ba(NO 3 ) 2 solution, control SO 4 2- and Ba 2+ The molar ratio is 1:1.2, and the high-sulfur, high-sodium and high-level radioactive waste liquid containing barite is obtained (the XRD of the sediment is shown in the attached figure 1 shown);

[0039] b. Ingredients: according to SiO 2 52.8%, B 2 o 3 19.6%, Na 2 O 4.4%, CaO 4.9%, Al 2 o 3 3.4%, MgO1.45%, TiO 2 1.45%, the component composition and mass percentage of the barite-containing high-sulfur, high-sodium and high-level radioactive waste liquid 12% in terms of waste oxides are taken from each component;

[0040] c. Mixing reaction: After mixing the raw materials, put them in a furnace (for example: muffle furnace or glass melting furnace, etc.) and heat-preserv...

Embodiment 3

[0042] A method for preparing a high-sulfur, high-sodium, high-level radioactive waste liquid glass-ceramic solidified body, the steps are:

[0043] a. Prepare barite-containing high-sulfur, high-sodium and high-level radioactive waste liquid: add Ba(NO 3 ) 2 solution, control SO 4 2- and Ba 2+ The molar ratio is 1:1.4, and the high-sulfur high-sodium high-level radioactive waste liquid containing barite and barium nitrate is obtained (the XRD of the sediment is shown in the attached figure 2 shown);

[0044] b. Ingredients: according to SiO 2 51.6%, B 2 o 3 19.1%, Na 2 O 4.3%, CaO 4.8%, Al 2 o 3 3.36%, MgO1.42%, TiO 2 1.42%, the component composition and mass percentage of the barite-containing high-sulfur, high-sodium and high-level radioactive waste liquid 14% in terms of waste oxides are taken from each component;

[0045] c. Mixing reaction: After mixing the raw materials, put them in a furnace (for example: muffle furnace or glass melting furnace, etc.) ...

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Abstract

The invention discloses a preparation method for a high-sulfur, high-sodium and high-level liquid waste glass-ceramic solidifier. The method is characterized in that a Ba(NO3)2 solution is added intoa high-sulfur, high-sodium and high-level liquid waste so that the molar ratio of SO4(2-) to Ba(2+) can be 1:(1-1.5), and high-sulfur, high-sodium and high-level liquid waste containing barite is obtained; raw materials SiO2, B2O3, Na2O, CaO, Al2O3, MgO, TiO2 and the barite-containing high-sulfur, high-sodium and high-level liquid waste are taken; the raw materials are mixed, then the mixture is placed in a furnace for calcination for 1-2 hour at 800-850 DEG C, molten at 1000-1150 DEG C for 2-3 hours, annealed at 450-500 DEG C for 1-2 hour and then naturally cooled to the room temperature, andthe high-sulfur, high-sodium and high-level liquid waste glass-ceramic solidifier is obtained. The melting temperature is low, the prepared glass-ceramic solidifier has high containment for the high-sulfur, high-sodium and high-level liquid waste, the chemical stability is good and the practicability is high.

Description

technical field [0001] The invention belongs to the treatment and disposal of radioactive waste, and relates to a method for preparing a solidified body of high-sulfur, high-sodium and high-level radioactive waste liquid glass ceramics. The invention is particularly suitable for the solidification treatment of high-level radioactive waste liquid with relatively high sulfur and sodium contents. Background technique [0002] High-level radioactive waste liquid (referred to as high-level radioactive waste liquid) mainly comes from the raffinate produced by the co-decontamination cycle of uranium and plutonium in the reprocessing process of spent fuel accumulated in nuclear power generation (also known as irradiated nuclear fuel, that is, used nuclear fuel). With the characteristics of complex chemical composition, high radioactive level, and high biological toxicity, its safe handling and disposal has become one of the key factors affecting the sustainable development of nuclea...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/16
CPCG21F9/162
Inventor 吴浪肖继宗滕元成李玉香
Owner SOUTHWEAT UNIV OF SCI & TECH
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