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A kind of experimental method of solidifying radioactive graphite powder at room temperature

A technology of room temperature curing and experimental methods, which is applied in the fields of radioactive purification and nuclear engineering, which can solve the problems of immature technology, poor stability of plastic materials, and in-depth research, so as to avoid leakage problems, low shrinkage rate, and excellent anti-leaching Effects of Sex and Irradiation Properties

Active Publication Date: 2020-11-24
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Due to the many advantages of plastic solidification, some people tried to use plastic solidification to treat radioactive waste in the 1980s, but due to the poor stability of the plastic material itself and the immaturity of related technologies at that time, the corresponding research did not go further.

Method used

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  • A kind of experimental method of solidifying radioactive graphite powder at room temperature

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Experimental program
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Effect test

Embodiment 1

[0022] First prepare the Nd(NO 3 ) 3 , Sr(NO 3 ) 2 , CsNO 3 and Co(NO 3 ) 2 The simulated nuclide mixed feed liquid, so that the concentration of each ion in the feed liquid is 135.6g / LNd 3+ , 146.8g / LSr 2+ , 107.7g / LCs + and 128g / LCo 2+ ;The calculation method of package capacity is as follows:

[0023]

[0024] Under normal temperature conditions, weigh 15g of epoxy resin, 1.05g of nuclear graphite powder (200 mesh), 5g of T-31 phenalkamine curing agent (5% capacity); first mechanically stir the mixture of epoxy resin and graphite material for 10min , so that the epoxy resin and the graphite material are fully mixed, and the Nd(NO 3 ) 3 , Sr(NO 3 ) 2 , CsNO 3 and Co(NO 3 ) 2 Then add T-31 phenalkamine curing agent; continue to stir for 10 minutes; pour the flowable mixture into the mold, press the mold, and store it at room temperature; disassemble the mold after two weeks, and take out the cured body; When the radiation dose is not more than 10 6 Irradi...

Embodiment 2

[0026] Under normal temperature conditions, weigh 15g of epoxy resin, 3.6g of graphite powder for nuclear use (325 mesh), 5g of T-31 phenalkamine curing agent (capacity is 15.2%); first mechanically stir the mixture of epoxy resin and graphite material 30min, the epoxy resin and the graphite material are fully mixed, and the Nd(NO 3 ) 3 , Sr(NO 3 ) 2 , CsNO 3 and Co(NO 3 ) 2 100ul of the mixed material liquid, and then add T-31 phenalkamine curing agent; continue to stir for 15 minutes; pour the flowable mixture into the mold, press the mold, and store it at room temperature; disassemble the mold after two weeks, and take out the cured body; When the radiation dose is not more than 10 6 Irradiate the cured body under the condition of Gy, detect the chemical stability of the cured body; use the static immersion method to study the Nd of the cured body of epoxy resin-graphite material 3+ 、Sr 2+ 、Cs + and Co 2+ Ion leaching performance, detected after 42 days, simulated...

Embodiment 3

[0028] Under normal temperature conditions, weigh 15g of epoxy resin, 8.6g of nuclear graphite powder (400 mesh), 5g of T-31 phenalkamine curing agent (30% capacity); first mechanically stir the mixture of epoxy resin and graphite material 60min, the epoxy resin and the graphite material are fully mixed, and the Nd(NO 3 ) 3 , Sr(NO 3 ) 2 , CsNO 3 and Co(NO 3 ) 2 Then add T-31 phenalkamine curing agent; continue to stir for 30 minutes; pour the flowable mixture into the mold, press the mold, and store it at room temperature; disassemble the mold after two weeks, and take out the cured body; When the radiation dose is not more than 10 6 Irradiate the cured body under the condition of Gy, detect the chemical stability of the cured body; use the static immersion method to study the Nd of the cured body of epoxy resin-graphite material 3+ 、Sr 2+ 、Cs + and Co 2+ Ion leaching performance, detected after 42 days, simulated nuclide removes Cs before and after irradiation + T...

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Abstract

The invention discloses an experimental method for curing radioactive graphite powder at room temperature. The method comprises the following steps: taking a nuclear-used graphite powder as a cured material, firstly preparing a simulated nuclide mixed material liquid containing Nd(NO3)3, Sr(NO3)2, CsNO3 and Co(NO3)2, then mixing epoxy resin and the graphite powder, and performing even mixing by mechanical stirring; adding the simulated nuclide mixed material liquid in the stirring process, then adding a T-31 phenolic amine curing agent, and performing continuous stirring to form a flowable mixture; pouring the flowable mixture into a mould, pressing the mould, and performing storing at room temperature; and dismantling the mould, and taking out the cured body. The method is simple in operation, heating is not needed, the cost is low, and the leakage problem of radioactive materials is avoided. At room temperature, the containment of the radioactive graphite waste can reach to be 30%. When the irradiation dose is less than 106 Gy, the hardness, surface structure and simulated nuclide leaching resistance of the epoxy resin cured body are not significantly affected by irradiation, sothat the epoxy resin cured body prepared by the method has excellent leaching resistance and irradiation resistance.

Description

technical field [0001] The invention relates to a method for treating waste graphite powder of high-temperature gas-cooled reactor spent fuel elements, which is suitable for waste graphite powder of high-temperature gas-cooled reactor spent fuel elements under radioactive conditions, and belongs to the technical field of nuclear waste treatment. Background technique [0002] The reprocessing process is conducive to the separation and classification management of radioactive waste, which can reasonably control the problem of radioactive waste, reduce the toxicity of radioactive waste, and improve the safety of radioactive waste disposal. [0003] The treatment and disposal of radioactive waste is one of the key issues facing the development of nuclear energy, and radioactive graphite is an important part of reactor nuclear waste. High-temperature gas-cooled reactor spent fuel components can be effectively separated from graphite waste and fuel-coated particles through electro...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21F9/30
Inventor 文明芬王树威王建晨陈靖
Owner TSINGHUA UNIV
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