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

Patent metadata

Field	Value
Publication number	US-2020161014-A1
Application number	US-201816195021-A
Country	US
Kind code	A1
Filing date	Nov 19, 2018
Priority date	Nov 19, 2018
Publication date	May 21, 2020
Grant date	—

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.

First claim

1 . A method for producing a solidifying material for radioactive waste disposal, the method comprising:
a first step (S 100 ) of pulverizing radioactive concrete waste and separating aggregates and paste; and a second step (S 200 ) of using the paste to produce a solidifying raw material, wherein the second step (S 200 ) comprises:
a calcination treatment step (S 210 ) of calcining a mixture obtained by mixing an additional material with the paste;
a sintering treatment step (S 220 ) of sintering the mixture in a sintering furnace after the calcination treatment step (S 210 ); and
a rapid-cooling treatment step (S 230 ) of rapid-cooling the mixture to produce a clinker after the sintering treatment step (S 220 ).

2 . The method of claim 1 , wherein the second step (S 200 ) further comprises, after the rapid-cooling treatment step (S 230 ), a solidifying raw material preparation step (S 240 ) 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 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.

Assignees

• Korea Inst Civil Eng & Building Tech

Inventors

• Kim Do Gyeum
• Seo Eun A

Classifications

• C04B7/44

  Burning; Melting · CPC title

• C04B28/141

  containing dihydrated gypsum before the final hardening step, e.g. forming a dihydrated gypsum product followed by a de- and rehydration step · CPC title

• C04B7/47

  Cooling {; Waste heat management} · CPC title

• G21F9/304 Primary

  Cement or cement-like matrix (compositional aspects C04B) · CPC title

• C04B2111/00767

  for waste stabilisation purposes · CPC title