Method for producing solidifying material for radioactive waste disposal via recycling of radioactive concrete and method for disposing of radioactive waste using the same

Abstract

In accordance with the present invention, provided is a method for producing a solidifying material for radioactive waste disposal, the method including a first step (S100) of pulverizing radioactive concrete waste and separating aggregates and paste and a second step (S200) of using the paste to produce a solidifying raw material, wherein the second step (S200) includes a calcination treatment step (S210) of calcining a mixture obtained by mixing an additional material with the paste; a sintering treatment step (S220) of sintering the mixture in a sintering furnace after the calcination treatment step (S210); and a rapid-cooling treatment step (S230) of rapid-cooling the mixture after the sintering treatment step (S220) to produce a clinker.

Claims

1. A method for producing a solidifying material for radioactive waste disposal, the method comprising: a first step (S100) of pulverizing radioactive concrete waste and separating aggregates and paste; and a second step (S200) of using the paste to produce a solidifying raw material, wherein the second step (S200) comprises: a calcination treatment step (S210) of calcining a mixture obtained by mixing an additional material with the paste; a sintering treatment step (S220) of sintering the mixture in a sintering furnace after the calcination treatment step (S210); and a rapid-cooling treatment step (S230) of rapid-cooling the mixture to produce a clinker after the sintering treatment step (S220).

2. The method of claim 1, wherein the second step (S200) further comprises, after the rapid-cooling treatment step (S230), a solidifying raw material preparation step (S240) of pulverizing the clinker and mixing dihydrate gypsum to produce the solidifying raw material.

3. The method of claim 1, wherein the additional material comprises limestone; and an iron oxide.

4. The method of claim 3, wherein the additional material further comprises an alkali flux.

5. The method of claim 4, wherein the paste comprises SiO.sub.2 in an amount of 15 wt % to 30 wt %.

6. The method of claim 5, wherein the mixture has a lime saturation factor (LSF) of 0.83 to 1.00, a silica modulus (SM) of 2.3 to 3.5, and an iron modulus (IM) of 1.2 to 2.2.

7. The method of claim 6, wherein the alkali flux is sodium sulfate, wherein the sodium sulfate has a weight % of 1.5 to 3.5 relative to the clinker.

8. The method of claim 7, wherein the fineness of the clinker constituting the solidifying raw material is 2000 Blaine to 5000 Blaine.

9. A method for disposing of radioactive waste using a solidifying material produced by using the method for producing a solidifying material for radioactive waste disposal of claim 7, the method comprising: receiving the radioactive waste in a waste disposal container (10) and solidifying the radioactive waste by adding the solidifying material to the radioactive waste.

10. The method of claim 9, wherein aggregate which is not radioactivated among the aggregate is utilized as recycled aggregate.

Description

BRIEF DESCRIPTION OF THE DRAWINGS

(1) FIG. 1 is a view showing a disposal process of conventional radioactive concrete.

(2) FIG. 2 is a view showing a process of producing a solidifying material via recycling of radioactive concrete, and disposing of radioactive waste by using the solidifying material produced, in accordance with an embodiment of the present invention.

(3) FIG. 3 is a block diagram for a solidifying material in accordance with an embodiment of the present invention.

MODE FOR CARRYING OUT THE INVENTION

(4) Embodiments of a method for producing a solidifying material for radioactive waste disposal via recycling of radioactive concrete and a method for disposing of radioactive waste in accordance with the present invention will be described in detail with reference to the accompanying drawings, and in describing the present invention with reference to the accompanying drawings, the same or corresponding components are denoted by the same reference numerals, and redundant description thereof will not be provided herein.

(5) In addition, terms such as first and second used below are merely reference numerals for distinguishing the same or corresponding components, and the same or corresponding components are not limited by the terms of first, second, and the like.

(6) In addition, the term “coupling”, in the contact relationship between the respective components, does not mean only that the components are in direct physical contact with each other, but it is used as a concept including the case where other components are interposed between the respective components and the components are in contact with the other components.

(7) The present invention relates to a method for efficiently disposing of radioactive waste, by which producing a solidifying material can be produced by recycling radioactive concrete and disposing of radioactive waste by using the solidifying material produced (FIG. 2).

(8) A method for producing a solidifying material for radioactive waste disposal in accordance with the present invention includes a first step (S100) of pulverizing radioactive concrete waste and separating aggregate and paste, and a second step (S200) of using the paste to produce a solidifying raw material (FIG. 2).

(9) Generally, in the case of radioactive concrete exposed to neutrons, radioactive elements (cobalt, europium) are mostly present in a paste portion, and are not included in an aggregate portion which account for a volume of 60% or more in concrete.

(10) Therefore, the aggregate and the paste included in radioactive concrete are separated, and then the aggregate is recycled as clean aggregate and the paste is recycled as a solidifying material for radioactive waste disposal, so that the volume of concrete waste to be disposed of may be reduced to 30% or less.

(11) It is preferable that the aggregate be separated until the amount of SiO.sub.2 included in the paste reaches 15 wt % to 30 wt %.

(12) The second step (S200) may include a calcination treatment step (S210) of calcining a mixture obtained by mixing an additional material with the paste, a sintering treatment step (S220) of sintering the mixture in a sintering furnace after the calcination treatment (S210), a rapid-cooling treatment step (S230) of rapid-cooling the mixture after the sintering treatment step (220) to produce a clinker, and a solidifying raw material preparation step (240) of producing a solidifying material by pulverizing the clinker and mixing a dihydrate gypsum to produce a solidifying raw material (FIG. 2).

(13) In the calcination treatment step (210), the mixture is dried and pulverized, and then calcination treatment is performed at a temperature of 900° C. to 1000° C.

(14) In the sintering treatment step (S220), the mixture subjected to the calcination treatment step is sintered in the sintering furnace at a temperature of 1250° C. to 1350° C.

(15) The mixture subjected to the sintering treatment step (S220) is rapid-cooled to produce a clinker (S230).

(16) The clinker is pulverized to form a solidifying raw material (S240).

(17) The fineness of the clinker constituting the solidifying raw material is preferably 2000 Blaine to 5000 Blaine.

(18) The solidifying raw material has properties of hydraulic regenerated cement and is added to the waste disposal container together with the radioactive waste and solidified as described later.

(19) In the case of filling the waste disposal container by using the solidifying material in accordance with the present invention, it was possible to secure a strength of 3.44 (MPa) or more as prescribed by the law (regulations on radioactive waste acquisition method).

(20) The additional material in accordance with the present invention may include limestone and iron oxide.

(21) In addition, the additional material may further include an alkali flux.

(22) In this case, the alkali flux may be sodium sulfate, and the sodium sulfate preferably have a weight % of 1.5 to 3.5 relative to the clinker.

(23) Generally, the alkali flux added to a sintering process at a high temperature reacts with calcium oxide or aluminum oxide to produce a crude clinker mineral, thereby contributing to exhibition of the early strength of cement.

(24) However, the alkali flux has a disadvantage of shortening the solidifying time of cement and adversely affecting the final strength in a long-term viewpoint. Therefore, it is general that the alkali flux is not added in the production of the cement.

(25) However, the solidifying material used in radioactive waste disposal, unlike general cement, is required to secure stability which is capable of securing physical properties of strength manifestation as a stable solidifying material in the early stage and minimizing occurrence of cracks due to shrinkage or crystal structure change after the early reaction.

(26) Therefore, in the present invention, unlike general cement, the alkali flux is added in the production of the solidifying material, thereby securing an effect that the effect of early strength manifestation and the long-term reactivity are lowered to be capable of stable waste storage.

(27) Sodium sulfate is a compound of alkali (Na.sub.2O) and sulfide (SO.sub.3), and may be liquefied at a low temperature to serve as a flux for lowering the sintering temperature of the clinker. Accordingly, the sodium sulfate may provide an effect in which the sintering temperature of the clinker is lowered by 100° C. or more compared with the sintering temperature of a general Portland cement clinker.

(28) In addition, since the sodium sulfate serving as a crude flux includes sulfide ions, soluble anhydrous gypsum is formed at a high temperature in the sintering process, and thus an expandable Ettringite hydrate is formed at the time of hydration to obtain a shrinkage reduction effect of the cured solidifying material.

(29) It is preferable that the sodium sulfate be included in an amount of 1.5 wt % to 3.5 wt % relative to the clinker.

(30) The mixture in accordance with the present invention preferably have a lime saturation factor (LSF) of 0.83 to 1.00, a silica modulus (SM) of 2.3 to 3.5, and an iron modulus (IM) of 1.2 to 2.2.

(31) The solidifying material produced in accordance with an embodiment of the present invention is added to the waste disposal container together with radioactive waste, thereby being capable of exhibiting the strength prescribed by the law.

(32) While the present invention has been particularly shown and described with reference to exemplary embodiments thereof, it is to be understood that the invention is not limited to the disclosed exemplary embodiments, but, on the contrary, it is to be understood that the technical scope of the present invention and the technical spirit of the present invention are all included in the scope of the present invention.