Looking for breakthrough ideas for innovation challenges? Try Patsnap Eureka!

Method for preparing high-radioactivity nuclear waste glass solidified base material

A vitrification and high-radioactivity technology, which is applied in the field of preparation of high-radioactive nuclear waste vitrification substrates, can solve the problems of low sulfur solubility, achieve good stability, achieve large-scale promotion and application, and realize the effects of resource utilization

Active Publication Date: 2013-08-28
DE RUISEN NANTONG COMPOSITE MATERIAL CO LTD
View PDF3 Cites 21 Cited by
  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, for high-level waste liquids containing higher concentrations of sulfate radicals, sulfur often becomes the limiting factor for waste containment capacity due to the low solubility of sulfur in borosilicate melts

Method used

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
View more

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0015] Step (1). Adjust the chemical composition of the black and white TV CRT screen glass, so that the percentage content of each component in the CRT screen glass is as follows: 45% SiO 2 , 14﹪B 2 o 3 , 10%Al 2 o 3 , 2.5﹪CaO, 13﹪Na 2 O, 4﹪Fe 2 o 3 , 11.5﹪PbO;

[0016] Step (2). Put the adjusted chemical composition of the CRT screen glass into a roller ball mill to grind and mix evenly, and melt it at 1100°C for 4 hours to fully melt it into glass liquid;

[0017] Step (3). Cast the molten glass in a mold preheated to 700°C, and cool to shape;

[0018] Step (4). Put the molding into an annealing furnace at 550° C. for 1 h, and then cool it down to room temperature naturally to obtain a high-radioactive nuclear waste vitrification substrate.

Embodiment 2

[0020] Step (1). Adjust the chemical composition of the CRT cone glass so that the percentages of each component in the CRT cone glass are as follows: 60% SiO 2 , 7﹪B 2 o 3 , 4﹪Al 2 o 3 , 0.2﹪CaO, 6﹪Na 2 O, 1% Fe 2 o 3 , 21.8﹪PbO;

[0021] Step (2). Put the adjusted chemical composition of the CRT cone glass into a roller ball mill to grind and mix evenly, and melt it at 980°C for 2 hours to fully melt it into glass liquid;

[0022] Step (3). Cast the molten glass in a mold preheated to 850°C, and cool to form;

[0023] Step (4). Put the molding into an annealing furnace at 400° C. for 3 h, and then cool it down to room temperature naturally to obtain a high-radioactive nuclear waste vitrification substrate.

Embodiment 3

[0025] Step (1). Adjust the chemical composition of the lamp glass so that the percentage of each component in the lamp glass is as follows: 58.5% SiO 2 , 9﹪B 2 o 3 、6﹪Al 2 o 3 , 1.5﹪CaO, 12﹪Na 2 O, 3% Fe 2 o 3 , 10﹪PbO;

[0026] Step (2). Put the adjusted chemical composition of the lamp glass into a roller ball mill to grind and mix evenly, and melt it at 1000°C for 3 hours to fully melt it into glass liquid;

[0027] Step (3). Cast the molten glass in a mold preheated to 750°C, and cool to shape;

[0028] Step (4). Put the molding into an annealing furnace at 450° C. for 2 h, and then cool it down to room temperature naturally to obtain a high-radioactive nuclear waste vitrification substrate.

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More

PUM

No PUM Login to View More

Abstract

The invention discloses a method for preparing a high-radioactivity nuclear waste glass solidified base material. For a high-radioactivity waste liquid containing high concentration of sulfate radicals, the dissolubility of sulfur in a borosilicate melt is low, and as a result, sulfur is always a limiting factor for waste loading quantity. A separated yellow phase can be generated during founding and consequently the nuclide loading and isolating functions of a glass solidified body are damaged seriously. The method comprises the steps of: adjusting the chemical components of waste lead-containing glass; evenly mixing the components, melting the components for 2-4 hours at the temperature of 980-1100 DEG C so as to completely melt the components to form molten glass; pouring the molten glass in a mould for shaping at the temperature of 700-850 DEG C; and placing the shaped glass in an annealing furnace at the temperature of 400-550 DEG C and preserving heat for 1-3 hours, thereby obtaining the high-radioactivity nuclear waste glass solidified base material. According to the method, the novel radioactivewaste glass solidified base material is prepared from the waste lead-containing glass as a main raw material by adjusting the chemical components of the glass, so that the waste is turned to be profitable, the resource utilization of the lead-containing glass is realized, and the glass solidified body is good in stability and does not generate the yellow phase easily during founding.

Description

technical field [0001] The invention belongs to the field of radioactive waste treatment and disposal, in particular to a method for preparing a high-radioactive nuclear waste vitrified base material. Background technique [0002] Nuclear power plants will inevitably produce some radioactive waste while using nuclear energy to generate electricity. This type of waste has a strong destructive effect on the natural environment and organisms. Therefore, how to effectively treat and dispose of nuclear waste becomes the key to the safe use of nuclear energy. Immobilization of nuclear waste is an important method to deal with high-level radioactive waste. The current solidification technologies include ceramic solidification, glass-ceramic solidification, glass solidification, artificial rock solidification and self-propagating high-temperature solidification. Ceramic solidification has a large containment capacity for radioactive elements in high-level radioactive waste, and crys...

Claims

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More

Application Information

Patent Timeline
no application Login to View More
IPC IPC(8): C03C3/108
Inventor 姚志通黄进刚
Owner DE RUISEN NANTONG COMPOSITE MATERIAL CO LTD
Who we serve
  • R&D Engineer
  • R&D Manager
  • IP Professional
Why Patsnap Eureka
  • Industry Leading Data Capabilities
  • Powerful AI technology
  • Patent DNA Extraction
Social media
Patsnap Eureka Blog
Learn More
PatSnap group products

Browse by: Latest US Patents, China's latest patents, Technical Efficacy Thesaurus, Application Domain, Technology Topic, Popular Technical Reports.

© 2024 PatSnap. All rights reserved.Legal|Privacy policy|Modern Slavery Act Transparency Statement|Sitemap|About US| Contact US: help@patsnap.com