Method for producing solidified radioactive waste

Patent metadata

Field	Value
Publication number	US-11120922-B2
Application number	US-201716308619-A
Country	US
Kind code	B2
Filing date	Jun 22, 2017
Priority date	Jun 23, 2016
Publication date	Sep 14, 2021
Grant date	Sep 14, 2021

Abstract

The present invention provides solidified radioactive waste into which a titanium-containing adsorbent having a radioactive element adsorbed thereto is vitrified, the solidified radioactive waste being capable of confining a large amount of the titanium-containing adsorbent having a radioactive element adsorbed thereto, and furthermore elution of the radioactive element from the vitrified waste being suppressed. The method of the present application includes a step of heat-melting a mixture that includes a titanium-containing adsorbent having a radioactive element adsorbed thereto, a SiO2 source, and an M2O source (M represents an alkali metal element) to form vitrified waste. The titanium-containing adsorbent is preferably one or two or more kind such as silicotitanate, an alkali nonatitanate, and titanium hydroxide.

First claim

The invention claimed is:

1. A method for producing solidified radioactive waste, comprising heat-melting a mixture that comprises a titanium-containing adsorbent having a radioactive element adsorbed thereto, a SiO 2 source, and an M 2 O source (M represents an alkali metal element) to form vitrified waste,
wherein the SiO 2 source and the M 2 O source are each an alkali silicate.

2. The method for producing solidified radioactive waste according to claim 1 , wherein the titanium-containing adsorbent is one or two or more selected from the group consisting of silicotitanate, an alkali nonatitanate, and titanium hydroxide.

3. The method for producing solidified radioactive waste according to claim 1 , wherein the radioactive element is cesium and/or strontium.

4. The method for producing solidified radioactive waste according to claim 1 , wherein the alkali silicate is an anhydride.

5. The method for producing solidified radioactive waste according to claim 1 , wherein the alkali silicate is sodium metasilicate.

6. A method for producing solidified radioactive waste, comprising heat-melting a mixture that comprises a titanium-containing adsorbent having a radioactive element adsorbed thereto, a SiO 2 source, and an M 2 O source (M represents an alkali metal element) to form vitrified waste,
wherein the mixture comprises at least M 2 O: 15 to 35% by mass, TiO 2 : 25 to 50% by mass, and SiO 2 : 15 to 35% by mass.

7. The method for producing solidified radioactive waste according to claim 1 , wherein a melt-heating temperature is 1000° C. or more.

8. The method for producing solidified radioactive waste according to claim 1 , wherein the mixture further comprises a metal oxide source comprising one or two or more metal elements selected from the group consisting of Zr, Al, Nb, Zn, Ca, and Mg.

Assignees

• Nippon Chemical Ind

Inventors

• Kinose Yutaka
• Miyabe Shinsuke

Classifications

• G21F9/305 Primary

  Glass or glass like matrix (C03B5/005 takes precedence; compositional aspects C03C) · CPC title

• B01J20/10

  comprising silica or silicate · CPC title

• B01J20/0211

  Compounds of Ti, Zr, Hf · CPC title

• G21F9/12 Primary

  by absorption; by adsorption; by ion-exchange · CPC title

• B01J2220/42

  Materials comprising a mixture of inorganic materials (materials coated or impregnated on a carrier B01J20/32) · CPC title