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Treatment method of radioactive spent ion exchange resin

A technology of ion exchange resin and treatment method, which is applied in the field of radioactive waste ion exchange resin treatment, and can solve the problems of reducing the volume reduction ratio of radioactive waste ion exchange resin, increasing the production of radioactive wastewater, and leakage of radioactive waste.

Pending Publication Date: 2022-04-05
TSINGHUA UNIV +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

There are two disadvantages in this thermal overpressure method: one is that non-radioactive polluted resin powder is added in the hot pressing process, which not only increases the cost, but also because the volume of the resin powder itself exceeds the total volume of the voids between the resin particles, The volume reduction ratio of the radioactive waste ion exchange resin is reduced; the second is that the pressed resin pancake has no mechanical strength (adding or not adding resin powder has no mechanical strength), if there is no metal shell, it will be completely pulverized within three hours, if the metal The enclosure is damaged, and the radioactive waste inside is very vulnerable to leakage
However, the disadvantage of this process is that the introduction of ball milling not only increases the process, but also easily causes pollution to the working environment
In order to improve the efficiency of ball milling, a certain amount of water needs to be added during the ball milling process, which further increases the amount of radioactive waste water produced

Method used

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  • Treatment method of radioactive spent ion exchange resin
  • Treatment method of radioactive spent ion exchange resin
  • Treatment method of radioactive spent ion exchange resin

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0046] Take by weighing 5 grams of polyurethane (MDI trimer), add 1.5 grams of triethylene glycol at room temperature and stir quickly, then add 100 grams of radioactive waste ion exchange resin dried to constant weight at 160 ° C and cooled to room temperature, stir After uniformity, transfer to a mold (diameter of the mold is 53mm), and press at 130°C and 130Bar pressure for 150 minutes. The resin block was taken out, and the measured geometric dimensions of the resin block were 45 mm in height, 53.4 mm in diameter, 3.69 in volume reduction ratio, and 32 MPa in compressive strength.

[0047] In the present invention, the volume reduction ratio is equal to the solid volume of the radioactive waste ion exchange resin before treatment divided by the volume of the resin block obtained after treatment. The compressive strength is obtained by testing according to the method specified in the standard GB 14569.1-2011 "Performance requirements for low and medium level radioactive was...

Embodiment 2

[0049] Weigh 10 grams of polyurethane (MDI trimer), add 1.15 grams of 1,6-hexanediol at room temperature, mix quickly and uniformly, then add 110 grams of radioactive waste ions dried at 160°C to constant weight and cooled to room temperature The resin was exchanged, stirred evenly, transferred to a mold (diameter of the mold was 53mm), and pressed at 130°C and 130Bar pressure for 150 minutes. The resin block was taken out, and the geometric dimensions of the resin block were measured to be 50 mm in height, 53.4 mm in diameter, 3.65 in volume reduction ratio, and 31.7 MPa in compressive strength.

Embodiment 3

[0051] Weigh 5 grams of epoxy resin E51, add 1.8 grams of polyethyleneimine, stir evenly, pour 100 grams of radioactive waste ion exchange resin that has been dried at 160°C to constant weight and cooled to room temperature, stir evenly, and then put the resin- The binder mixture was transferred into a mold (53mm diameter mold) and then pressed at 130°C under 130 Bar pressure for 150 minutes. The resin block was taken out, and the measured geometric dimensions of the resin block were 48.7 mm in height, 53.0 mm in diameter, 3.63 in volume reduction ratio, and 34.5 MPa in compressive strength.

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Abstract

The invention provides a treatment method of radioactive spent ion exchange resin, and relates to the technical field of environmental protection. Non-radioactive contamination resin powder is not additionally added, and the adhesive only occupies gaps among radioactive spent ion exchange resin particles, so that the volume reduction ratio is high; according to the invention, the non-radioactive resin powder is bonded by using the adhesive, and the obtained resin block has high strength, the compressive strength is greater than 30 MPa and is far higher than the compressive strength requirement of 7 MPa of a cement solidified body, the resin briquette does not have hashing even if water soaking occurs in an accident, and the resin briquette has good stability under the condition that an outer package is damaged. The resin does not generate radioactive leakage due to pulverization; moreover, as the resin block cannot be pulverized, an inner barrel can be omitted, the pressing block can be directly placed on an outer package of a steel barrel with a proper size, and the operation procedures and the cost are reduced.

Description

technical field [0001] The invention relates to the technical field of environmental protection, in particular to a method for treating radioactive waste ion exchange resins. Background technique [0002] Ion exchange resin is a commonly used wastewater treatment agent in nuclear power plants, and is generally used in the treatment of low-level radioactive wastewater. There are two main ways for nuclear power plants to dispose of waste ion exchange resins: cement solidification and thermal overpressure. [0003] Cement solidification blocks are resistant to water and can remain stable in a wide temperature range, so cement solidification is an industry-recognized method for immobilizing radionuclides. However, an obvious disadvantage of cement solidification is that the volume of solid waste increases greatly, which is obviously incompatible with the requirements of nuclear power plant solid waste reduction. Therefore, only a few nuclear power plants are still in use world...

Claims

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Application Information

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IPC IPC(8): G21F9/30
Inventor 王毅杨静远施维泽周小青叶沥靳海睿刘志远张岩刘慧春
Owner TSINGHUA UNIV
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