Low temperature decontamination of tritiated water

Patent metadata

Field	Value
Publication number	US-12415146-B2
Application number	US-202217848878-A
Country	US
Kind code	B2
Filing date	Jun 24, 2022
Priority date	Jun 24, 2022
Publication date	Sep 16, 2025
Grant date	Sep 16, 2025

Abstract

Methods and systems directed to the separation of tritium from an aqueous stream are described. The separation method is a multistage method that includes a purification stage during which tritium of a tritium-contaminated aqueous stream is adsorbed onto a cooled and wet separation phase, a regeneration stage during which the adsorbed tritium is exchanged with hydrogen in a gaseous stream to regenerate the separation phase and provide a gaseous stream with a high tritium concentration, and a third stage during which the tritium of the gaseous stream is separated from the gaseous stream as a gaseous tritium product.

First claim

What is claimed is:

1. A process for removal and recovery of tritium from tritium-contaminated water, the process comprising:
cooling an interior volume of an enrichment column to a temperature of about 20° C. or less, the interior volume containing a separation phase and a catalyst;
contacting the separation phase within the cooled interior volume with an aqueous stream comprising tritium-contaminated water and a carrier gas, wherein upon the contact, tritium of the aqueous stream is preferentially adsorbed onto the surface of the separation phase, thereby purifying the aqueous stream;
subsequently, contacting the separation phase comprising the adsorbed tritium with a regeneration stream, the regeneration stream comprising protium and/or deuterium in the form of hydrogen gas, deuterium gas, hydrogen deuteride, or mixtures thereof, the catalyst of the enrichment column catalyzing an isotopic exchange between the adsorbed tritium and the protium and/or the deuterium of the regeneration stream to form a tritium-enriched gaseous stream; and
separating the tritium from the tritium-enriched gaseous stream.

2. The process of claim 1 , the separation phase comprising a hydrophilic material that comprises a surface area of about 100 square meters per gram or greater and/or comprises pores having an average pore diameter of about 500 Angstroms or less.

3. The process of claim 1 , the separation phase comprising a type A zeolite, a type X zeolite, a type Y zeolite, a metal oxide, or a combination thereof.

4. The process of claim 3 , the separation phase comprising NaY zeolite.

5. The process of claim 1 , the process comprising cooling the interior volume of the enrichment column to a temperature of about 10° C. or less.

6. The process of claim 1 , wherein the regeneration stream is at ambient temperature at contact with the separation phase.

7. The process of claim 1 , wherein the interior volume of the enrichment column is wet prior to contacting the separation phase with the aqueous stream.

8. The process of claim 7 , wherein the interior volume of the enrichment column is at a saturated water vapor pressure prior to contacting the separation phase with the aqueous stream.

9. The process of claim 7 , further comprising injecting non-contaminated water into the enrichment column volume prior to contacting the separation phase with the aqueous stream.

10. The process of claim 9 , wherein the separation phase remains wet during contact of the separation phase with the regeneration stream.

11. The process of claim 1 , wherein the tritium is recovered from the tritium-enriched gaseous stream according to a thermal cycling absorption process.

12. The process of claim 1 , the method further comprising bubbling the carrier gas through a source of the tritium-contaminated water prior to contacting the separation phase with the aqueous stream.

13. The process of claim 1 , the method further comprising injecting a liquid stream comprising the tritium-contaminated water into the enrichment column in conjunction with a gaseous stream comprising the carrier gas.

14. The process of claim 1 , wherein the tritium-enriched gaseous stream comprises tritium in an amount of about 50 parts per million or greater.

15. The process of claim 1 , further comprising a second enrichment column, wherein
contemporaneous with contacting the separation phase of the enrichment column of claim 1 with the aqueous stream, a separation phase of the second enrichment column is contacted with the regeneration stream; and
contemporaneous with contacting the separation phase of the enrichment column of claim 1 with the regeneration stream, the separation phase of the second enrichment column is contacted with the aqueous stream.

16. A system for removal and recovery of tritium from a tritium-contaminated aqueous stream, the system comprising:
an enrichment column containing a separation phase and a catalyst within an interior volume, the enrichment column including a first inlet at a first end of the enrichment column configured for receiving the tritium-contaminated aqueous stream and a first outlet at a second end of the enrichment column for exit of a purified aqueous stream, the enrichment column further comprising a second inlet at the second end of the enrichment column for receiving a gaseous regeneration stream that includes protium and/or deuterium in the form of hydrogen gas, deuterium gas, hydrogen deuteride gas, or mixtures thereof, and a second outlet at the first end of the enrichment column for exit of a tritium-enriched gaseous flow;
a cooling system in communication with an interior volume of the enrichment column; and
a thermal cycling absorption column in fluid communication with the second outlet of the enrichment column, wherein the thermal cycling absorption column comprises an inverse separation column that includes a separation material that preferentially adsorbs tritium at an absorption temperature and that releases the adsorbed tritium at a release temperature.

17. The system of claim 16 , further comprising a water injection port configured to inject non-contaminated water into the interior volume of the enrichment column.

18. The system of claim 16 , further comprising a second enrichment column in fluid communication with the thermal cycling absorption column, wherein the second enrichment column is configured for parallel operation with the enrichment column of claim 15 .

19. The system of claim 18 , wherein the second enrichment column is configured for countercurrent operation to the enrichment column of claim 16 .

20. The system of claim 16 , wherein the first inlet is configured to receive a liquid stream comprising tritium-contaminated water and a gaseous stream comprising a carrier gas.

21. The system of claim 16 , wherein the first inlet is configured to receive the tritium-contaminated aqueous stream in the form of a vapor stream comprising tritium- contaminated vapor in a carrier gas.

Assignees

• Battelle Savannah River Alliance Llc
• Savannah River Nuclear Solutions Llc

Inventors

• Xiao Xin
• Angelette Lucas M
• Sessions Jr Henry T
• Rabun Iii Robert L
• Klein James E
• Kvartek John

Classifications

• B01J20/28052

  Several layers of identical or different sorbents stacked in a housing, e.g. in a column · CPC title

• C01B4/00

  Hydrogen isotopes; Inorganic compounds thereof prepared by isotope exchange, e.g. NH3 + D2 → NH2D + HD · CPC title

• B01J20/283

  based on silica · CPC title

• B01J20/3408

  of aluminosilicate molecular sieves · CPC title

• B01J20/3466 Primary

  with steam · CPC title