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Preparation method of molybdenum-containing radioactive waste glass ceramic solidified body

A technology of radioactive waste and glass ceramics, which is applied in the solidification treatment of radioactive waste, the treatment and disposal of radioactive waste, and can solve the problems of the overall solidified amount of molybdenum yellow relative to the adverse effect on the stability of the solidified body, and achieve good treatment and disposal effects and practicability Strong, simple preparation process

Pending Publication Date: 2022-05-10
SOUTHWEAT UNIV OF SCI & TECH
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] The purpose of the present invention is to overcome the low solubility of molybdenum in the prior art, which limits the overall solidification amount of radioactive waste, and the yellow phase has an adverse effect on the stability of solidified bodies, and provides a molybdenum-containing molybdenum with high solubility and good chemical stability. Preparation method of molybdenum radioactive waste glass ceramic solidified body

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  • Preparation method of molybdenum-containing radioactive waste glass ceramic solidified body
  • Preparation method of molybdenum-containing radioactive waste glass ceramic solidified body
  • Preparation method of molybdenum-containing radioactive waste glass ceramic solidified body

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Embodiment 1

[0030] A method for preparing a molybdenum-containing radioactive waste glass-ceramic solidified body, the steps are:

[0031] a. According to the mass percentage of pyroxene 98% and simulated radioactive waste 2%, weigh 29.4g of raw pyroxene, MoO 3 0.6g, the pyroxene and the simulated radioactive waste are ball-milled and mixed uniformly to obtain a mixture; the simulated molybdenum-containing radioactive waste is MoO 3 ;

[0032] b. Heat the mixture at a rate of 10°C / min to 1400°C for heat preservation and melting (heating and melting in a high-temperature box furnace) for 3 hours to obtain a liquid melt, and cast the liquid melt on a preheated mold or graphite plate Then (quickly) transfer the glass block to another annealing furnace for annealing. The annealing process is: keep warm in the annealing furnace at 600°C for 2 hours, and drop to room temperature with the furnace (that is, cooling), that is Prepare molybdenum-containing radioactive waste vitrified body;

[00...

Embodiment 2

[0035] A method for preparing a molybdenum-containing radioactive waste glass-ceramic solidified body, the steps are:

[0036] a. According to the mass percentage of 96% pyroxene and 4% simulated radioactive waste, weigh 28.8g raw pyroxene, MoO 3 1.2g, the pyroxene and the simulated radioactive waste are ball-milled and mixed uniformly to obtain a mixture; the simulated molybdenum-containing radioactive waste is MoO 3 ;

[0037] b. Heat the mixture at a rate of 10°C / min to 1400°C for heat preservation and melting (heating and melting in a high-temperature box furnace) for 3 hours to obtain a liquid melt, and cast the liquid melt on a preheated mold or graphite plate Then (quickly) transfer the glass block to another annealing furnace for annealing. The annealing process is: keep warm in the annealing furnace at 600°C for 2 hours, and drop to room temperature with the furnace (that is, cooling), that is Prepare molybdenum-containing radioactive waste vitrified body;

[0038]...

Embodiment 3

[0040] A method for preparing a molybdenum-containing radioactive waste glass-ceramic solidified body, the steps are:

[0041] a. According to the mass percentage of 92% pyroxene and 8% simulated radioactive waste, weigh 27.6g raw pyroxene, MoO 3 2.4g, the pyroxene and simulated radioactive waste are ball-milled and mixed uniformly to obtain a mixture; the simulated molybdenum-containing radioactive waste is MoO 3 ;

[0042] b. Heat the mixture at a rate of 10°C / min to 1400°C for heat preservation and melting (heating and melting in a high-temperature box furnace) for 3 hours to obtain a liquid melt, and cast the liquid melt on a preheated mold or graphite plate Then (quickly) transfer the glass block to another annealing furnace for annealing. The annealing process is: keep warm in the annealing furnace at 600°C for 2 hours, and drop to room temperature with the furnace (that is, cooling), that is Prepare molybdenum-containing radioactive waste vitrified body;

[0043] The...

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Abstract

The invention discloses a preparation method of a molybdenum-containing radioactive waste glass ceramic solidified body, which is characterized by comprising the following steps: heating a raw material pyroxene to 1390-1500 DEG C, preserving heat and melting for 3-4 hours, cooling to obtain a glass block, and crushing to obtain pyroxene glass powder; the method comprises the following steps: uniformly mixing 92-95% by mass of pyroxene glass powder and 5-8% by mass of simulated radioactive waste through ball milling to obtain a mixture; the molybdenum-containing radioactive waste is simulated to be MoO3; and heating the mixture to 1390-1450 DEG C, preserving heat and melting for 3-4 hours to obtain a liquid melt, and annealing and cooling to obtain the molybdenum-containing radioactive waste glass ceramic solidified body. The molybdenum-containing radioactive waste glass ceramic solidified body prepared by adopting the method has large capacity on molybdenum, has good chemical stability, and is suitable for solidification treatment of molybdenum-containing radioactive waste discharged in the nuclear industry and the like.

Description

technical field [0001] The invention belongs to the treatment and disposal of radioactive waste, and relates to a method for preparing a molybdenum-containing radioactive waste glass ceramic solidified body. The invention is suitable for solidification treatment of molybdenum-containing radioactive waste discharged from the nuclear industry and the like. Background technique [0002] The development and utilization of nuclear energy has brought enormous economic and social benefits to mankind, and at the same time brought a large amount of radioactive waste generated from the reprocessing of spent fuel. These radioactive wastes contain more than 30 elements including actinides and fission nuclides. Hundreds of isotopes have the characteristics of strong radioactivity, high biological toxicity, long half-life of nuclides, and high corrosiveness, and their treatment and disposal have attracted more attention. [0003] In the prior art, the chemical properties of glass are sta...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C03C10/00G21F9/30
CPCC03C10/0063G21F9/305
Inventor 霍冀川徐冲张行泉霍泳霖
Owner SOUTHWEAT UNIV OF SCI & TECH
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