Stepwise chemical separation methods and systems using resin packed columns

Patent metadata

Field	Value
Publication number	US-12567510-B2
Application number	US-202217737737-A
Country	US
Kind code	B2
Filing date	May 5, 2022
Priority date	May 5, 2022
Publication date	Mar 3, 2026
Grant date	Mar 3, 2026

Abstract

A waste extraction system that includes a column set positioned between and fluidly coupled to an upstream segment of a main waste pathway and a column effluent tank, the column set having a uranium adsorption column fluidly coupled to a supporting adsorption column along the main waste pathway. The uranium adsorption column is upstream the supporting adsorption column. The waste extraction system also includes a strip waste pathway extending from the uranium adsorption column to the column effluent tank bypassing the supporting adsorption column, an anion exchange resin housed in the uranium adsorption column, and a cation exchange resin housed in the supporting adsorption column.

First claim

What is claimed is:

1 . A method of radionuclide waste extraction, the method comprising:
directing a waste stream from an upstream segment of a main waste pathway into a uranium adsorption column of a column set, wherein:
the column set further comprises a supporting adsorption column fluidly coupled to the uranium adsorption column along the main waste pathway and positioned downstream the uranium adsorption column; and
a strip waste pathway extends from the uranium adsorption column to a column effluent tank bypassing the supporting adsorption column;
adsorbing uranium from the waste stream onto an anion exchange resin housed in the uranium adsorption column; directing the waste stream from the uranium adsorption column into the supporting adsorption column; and adsorbing one or more target radionuclides onto a cation exchange resin housed in the supporting adsorption column, wherein the one or more target radionuclides comprise strontium-90 and cesium-137 and are present in the waste stream at lower quantities than uranium.

2 . The method of claim 1 , further comprising directing the waste stream from the supporting adsorption column to the column effluent tank, wherein the waste stream entering the column effluent tank comprises less than 0.04 curies per cubic meter of strontium-90 and less than 1 curie per cubic meter of cesium-137.

3 . The method of claim 1 , wherein the waste stream in the upstream segment of the main waste pathway comprises a gram/liter level of uranium that is at least 500 times greater than a gram/liter level of both strontium-90 and cesium-137.

4 . The method of claim 1 , wherein the one or more target radionuclides further comprise barium, cerium, lanthanum, molybdenum, sodium, neodymium, palladium, praseodymium, rubidium, rhodium, ruthenium, samarium, yttrium, zirconium, protactinium, or a combination thereof.

5 . The method of claim 1 , wherein the anion exchange resin housed in the uranium adsorption column adsorbs 90% or more of the uranium present in the waste stream.

6 . The method of claim 1 , wherein the waste stream in the upstream segment of the main waste pathway comprises 1 gram/liter of uranium or greater.

7 . The method of claim 1 , wherein the cation exchange resin housed in the supporting adsorption column adsorbs 90% or more of the one or more target radionuclides present in the waste stream.

8 . The method of claim 1 , wherein the supporting adsorption column is a first supporting adsorption column and the column set further comprises a second supporting adsorption column downstream the first supporting adsorption column along the main waste pathway, the second supporting adsorption column housing a cation exchange resin.

9 . The method of claim 8 , wherein the first supporting adsorption column and the second supporting adsorption column collectively adsorb 99% or more of the one or more target radionuclides present in the waste stream.

10 . The method of claim 1 , further comprising:
directing an elution acid into the uranium adsorption column to desorb uranium from the anion exchange resin, forming a uranium waste stream; and directing the uranium waste stream to the column effluent tank along the strip waste pathway.

11 . The method of claim 1 , wherein:
the cation exchange resin comprises cation exchange resin beads; the anion exchange resin comprises anion exchange resin beads; the cation exchange resin beads and the anion exchange resin beads are each polymer based; and the cation exchange resin beads and the anion exchange resin beads have an average diameter in a range of from 400 μm to 800 μm.

12 . The method of claim 1 , wherein uranium comprises from 40% to 60% of total radionuclides in the waste stream.

13 . The method of claim 1 , wherein a gram/liter level of uranium in the waste steam is at least 500 times greater than a gram/liter level of strontium-90 and cesium-137.

14 . A method of radionuclide waste extraction, the method comprising:
directing a waste stream from an upstream segment of a main waste pathway into a uranium adsorption column of a column set, wherein:
the waste stream in the upstream segment of the main waste pathway comprises 1 gram/liter of uranium or greater;
the column set further comprises a supporting adsorption column fluidly coupled to the uranium adsorption column along the main waste pathway and positioned downstream the uranium adsorption column; and
a strip waste pathway extends from the uranium adsorption column to a column effluent tank bypassing the supporting adsorption column;
adsorbing uranium from the waste stream onto an anion exchange resin housed in the uranium adsorption column; directing the waste stream from the uranium adsorption column into the supporting adsorption column; and adsorbing one or more target radionuclides onto a cation exchange resin housed in the supporting adsorption column, wherein the target radionuclides are present in the waste stream at lower quantities than uranium.

15 . The method of claim 14 , wherein the one or more target radionuclides comprise strontium-90 and cesium-137.

16 . The method of claim 14 , further comprising:
directing an elution acid into the uranium adsorption column to desorb uranium from the anion exchange resin, forming a uranium waste stream; and directing the uranium waste stream to the column effluent tank along the strip waste pathway.

17 . A method of radionuclide waste extraction, the method comprising:
directing a waste stream from an upstream segment of a main waste pathway into a uranium adsorption column of a column set, wherein:
the column set further comprises a supporting adsorption column fluidly coupled to the uranium adsorption column along the main waste pathway and positioned downstream the uranium adsorption column; and
a strip waste pathway extends from the uranium adsorption column to a column effluent tank bypassing the supporting adsorption column;
adsorbing uranium from the waste stream onto an anion exchange resin housed in the uranium adsorption column; directing the waste stream from the uranium adsorption column into the supporting adsorption column; adsorbing one or more target radionuclides onto a cation exchange resin housed in the supporting adsorption column, directing an elution acid into the uranium adsorption column to desorb uranium from the anion exchange resin, forming a uranium waste stream; and directing the uranium waste stream to the column effluent tank along the strip waste pathway, wherein the target radionuclides are present in the waste stream at lower quantities than uranium.

18 . The method of claim 17 , wherein the one or more target radionuclides comprise barium, cerium, cesium, lanthanum, molybdenum, sodium, neodymium, palladium, praseodymium, rubidium, rhodium, ruthenium, samarium, strontium, yttrium, zirconium, protactinium, or a combination thereof.

19 . The method of claim 17 , wherein the one or more target radionuclides comprise strontium-90 and cesium-137.

20 . A method of radionuclide waste extraction, the method comprising:
directing a waste stream from an upstream segment of a main waste pathway into a uranium adsorption column of a column set, wherein:
uranium comprises from 40% to 60% of total radionuclides in the waste stream;
the column set further comprises a supporting adsorption column fluidly coupled to the uranium adsorption column along the main waste pathway and positioned downstream the uranium adsorption c

Assignees

• Shine Technologies Llc

Inventors

• Momen Abdul
• Piechowicz Marek
• Mcsweeny Riley

Classifications

• B01D15/362 Primary

  Cation-exchange · CPC title

• B01D15/363

  Anion-exchange · CPC title

• B01D15/1871

  placed in series · CPC title

• C02F2101/006

  Radioactive compounds · CPC title

• B01J47/028

  with alternately arranged cationic and anionic exchangers · CPC title