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Glass substrate composition for incineration ash of combustible wastes with low and medium-level radioactivity, and glass curing body prepared from glass substrate composition

A glass matrix and vitrification technology, which is applied in glass manufacturing equipment, glass forming, manufacturing tools, etc., can solve the problems of special waste and complex high-level waste liquid

Active Publication Date: 2015-01-28
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Previously, vitrification was a complex and expensive technology, usually only used for high-level liquid waste and special waste that was difficult to treat with other technologies

Method used

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  • Glass substrate composition for incineration ash of combustible wastes with low and medium-level radioactivity, and glass curing body prepared from glass substrate composition
  • Glass substrate composition for incineration ash of combustible wastes with low and medium-level radioactivity, and glass curing body prepared from glass substrate composition
  • Glass substrate composition for incineration ash of combustible wastes with low and medium-level radioactivity, and glass curing body prepared from glass substrate composition

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Experimental program
Comparison scheme
Effect test

Embodiment 1

[0076] Determination of the main simulated components of the incineration ash of medium and low level radioactive combustible waste

[0077] A holistic consideration of the oxide composition in radioactive waste. It mainly simulates the oxide and nuclide composition of the remaining ash after incineration of absorbent paper, cotton product labor insurance, plastic cloth and rubber gloves in nuclear power plants. The main oxide content is obtained by chemical analysis, and the radionuclides are mainly considered fission products 137 Cs, 90 Sr and activation products 60 Co. The composition and content of the simulated waste are shown in Table 1 below.

[0078]

[0079] Among them, the data in the above table 1 is obtained on the basis of 100 parts by weight of each combustible waste incineration ash, and the CoO and Cs in the various simulated waste incineration ash are not listed in the above table 1 2 The contents of O and SrO are respectively 0.2wt% of the total amoun...

Embodiment 2-4

[0091] The treatment method of low-medium level radioactive cotton products: Weigh the corresponding raw materials for the components listed in the above table 1 and the following table 3 according to the proportion, and weigh 100 parts by weight of the glass matrix composition (according to the oxide Calculate), and weigh 60 parts of simulated waste (calculated by oxide) at the same time. The ingredients are ground and mixed evenly, put into corundum crucible, and sent to a box-type resistance furnace preheated to above 300°C for melting. Keep the temperature at 1100-1300°C for 2-5h, then pour it into a graphite tube that has been preheated at 400-600°C, then anneal in an annealing furnace at this temperature, and cool naturally in the furnace to room temperature.

[0092]

Embodiment 5-6

[0094] Treatment methods for medium and low level radioactive absorbent paper:

[0095] Weigh the corresponding raw materials for the components listed in the above Table 1 and the following Table 4 in parts by weight according to the proportion. For every 100 parts by mass of the glass matrix composition (calculated as oxides), 50 parts by mass of simulated waste (calculated as oxides) were weighed at the same time. The raw materials are finely ground in a mortar, mixed carefully, put into a corundum crucible, and sent to a box-type resistance furnace preheated to above 300°C for melting. Keep the temperature at 1100-1300°C for 2-5h, then pour it into a graphite tube that has been preheated at 400-600°C, then anneal in an annealing furnace at this temperature, and cool naturally in the furnace to room temperature.

[0096]

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Abstract

The invention discloses a glass substrate composition for incineration ash of combustible wastes with low and medium-level radioactivity, and a glass curing body prepared from the glass substrate composition. Aiming at the special physicochemical properties of the combustible wastes such as absorbent paper, cotton products, plastic cloth, rubber and the like which have low and medium-level radioactivity and are produced by nuclear facilities, the invention provides the glass substrate composition which is respectively suitable for the combustible wastes such as the absorbent paper, the cotton products, the plastic cloth and the rubber. The glass curing body can meet the requirements of weight loss ratio of a radioactive waste curing body, the density after soaking, the compressive strength, the shock strength and the irradiation resistance.

Description

technical field [0001] The invention belongs to the field of radioactive waste treatment and solidification, and in particular relates to a glass matrix composition used for incineration ash of medium and low-level radioactive combustible waste and a glass solidified body prepared therefrom. Background technique [0002] Low- and medium-level radioactive waste generated during the operation and decommissioning of nuclear facilities includes process waste and technical waste, with complex types and huge quantities. Taking the Daya Bay Nuclear Power Plant as an example, absorbent paper, cotton products, plastics and rubber account for more than 80% of its common technical waste. How to process and dispose of these combustible radioactive wastes is a challenging technical problem, and all advanced countries are currently conducting related technical research. [0003] For the treatment of low- and medium-level radioactive combustible waste, there are mainly compaction solidifi...

Claims

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Application Information

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IPC IPC(8): C03C3/091C03C6/00C03B19/02
CPCC03B19/02C03C1/002C03C3/091
Inventor 张劲松陈云明曹骐李已才冯伟伟李兵
Owner NUCLEAR POWER INSTITUTE OF CHINA
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