Radionuclide adsorbent, method of producing radionuclide adsorbent and production apparatus thereof

Patent metadata

Field	Value
Publication number	US-9682360-B2
Application number	US-201314135304-A
Country	US
Kind code	B2
Filing date	Dec 19, 2013
Priority date	Dec 20, 2012
Publication date	Jun 20, 2017
Grant date	Jun 20, 2017

Abstract

Granular crystalline silicotitanate (CST) is supplied from an adsorbent raw material supply apparatus into a caustic treatment apparatus. A sodium hydroxide solution of 1 Mol/L in a caustic agent supply apparatus is supplied into the caustic treatment apparatus with the granular CST supplied. After a predetermined quantity of the sodium hydroxide solution is supplied to the caustic treatment apparatus, the supply of the sodium hydroxide solution to the caustic treatment apparatus is stopped. The granular CST is left to stand for 0.5 hour in the state that it is immersed in the sodium hydroxide solution in the caustic treatment apparatus and is subjected to the caustic treatment. After that, the granular CST subjected to the caustic treatment is cleaned by cleaning water in a cleaning water supply apparatus. The respective adsorptive performances of cesium and strontium of the granular CST subjected to the caustic treatment are improved more.

First claim

What is claimed is:

1. A method of producing a radionuclide adsorbent, comprising the steps of:
forming powdery silicotitanate compounds into a formed silicotitanate compound;
storing said formed silicotitanate compound in a cage having a plurality of openings, wherein said formed silicotitanate compound is being held by said cage;
disposing said cage holding said formed silicotitanate compound into a vessel of a caustic treatment apparatus; and
bringing said formed silicotitanate compound into contact with a sodium hydroxide solution having a sodium hydroxide concentration within a range of 0.5 Mol/L or more but less than 2.0 Mol/L in said caustic treatment apparatus, wherein said sodium hydroxide solution is present in said vessel, and wherein said formed silicotitanate compound is immersed in said sodium hydroxide solution in said caustic treatment apparatus for 0.5 hour to 2 hours.

2. The method of producing a radionuclide adsorbent according to claim 1 , wherein said sodium hydroxide concentration of said sodium hydroxide solution in contact with said formed silicotitanate compound is within a range from 0.8 Mol/L to 1.5 Mol/L.

3. The method of producing a radionuclide adsorbent according to claim 1 , wherein said sodium hydroxide solution is supplied into said caustic treatment apparatus within a range from 5 L to 20 L per 1 kg of said formed silicotitanate compound put in said caustic treatment apparatus.

4. The method of producing a radionuclide adsorbent according to claim 1 , wherein said contact of said sodium hydroxide solution with said formed silicotitanate compound is performed by permitting said sodium hydroxide solution to continuously flow through said caustic treatment apparatus.

5. The method of producing a radionuclide adsorbent according to claim 1 , wherein the size of said opening is smaller than the size of said formed silicotitanate compound.

6. The method of producing a radionuclide adsorbent according to claim 1 , wherein said cage is a wire netting cage.

Assignees

• Hitachi Ge Nuclear Energy Ltd

Inventors

• Kani Yuko
• Asano Takashi

Classifications

• G21F9/12

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

• B01J20/0211

  Compounds of Ti, Zr, Hf · CPC title

• B01J20/3085

  Chemical treatments not covered by groups B01J20/3007 - B01J20/3078 · CPC title

• B01J20/10 Primary

  comprising silica or silicate · CPC title

• B01J20/3071

  Washing or leaching · CPC title