Radionuclide generation

Patent metadata

Field	Value
Publication number	US-2025034678-A1
Application number	US-202218717078-A
Country	US
Kind code	A1
Filing date	Dec 27, 2022
Priority date	Dec 31, 2021
Publication date	Jan 30, 2025
Grant date	—

Abstract

A radionuclide separating system for separating a 213Bi daughter radionuclide from a 225Ac parent radionuclide, the radionuclide separating system comprising: an inlet for loading a liquid solution comprising the 225Ac parent radionuclide onto a column; the column comprising a sorbent material wherein the sorbent material is capable of interacting with the 225Ac parent radionuclide and 213Bi daughter radionuclide so as to allow selective desorption of the 225Ac parent radionuclide and/or the 213Bi daughter radionuclide at a different moment in time; and an outlet for selectively obtaining the 213Bi daughter radionuclide based on the selective desorption of the 225Ac parent radionuclide and the 213Bi daughter radionuclide, wherein the sorbent material is a carbon-based sorbent material.

First claim

1 .- 15 . (canceled)

16 . A radionuclide separating system for separating a 213 Bi daughter radionuclide from an 225 Ac parent radionuclide, the radionuclide separating system comprising:
an inlet for loading a liquid solution comprising the 225 Ac parent radionuclide onto a column, the column comprising a sorbent material wherein the sorbent material is capable of interacting with the 225 Ac parent radionuclide and 213 Bi daughter radionuclide so as to allow selective desorption of the 225 Ac parent radionuclide and/or the 213 Bi daughter radionuclide at a different moment in time, and an outlet for selectively obtaining said 213 Bi daughter radionuclide based on said selective desorption of the 225 Ac parent radionuclide and the 213 Bi daughter radionuclide, wherein the sorbent material is a carbon-based sorbent material.

17 . The radionuclide separating system according to claim 16 , wherein the carbon-based sorbent material comprises an active material with one or more compounds containing one or more functional groups.

18 . The radionuclide separating system according to claim 16 , wherein the one or more functional groups are selected from:
one or more oxygen containing groups; and/or one or more sulfur containing groups; and/or one or more phosphorous containing groups.

19 . The radionuclide separating system according to claim 16 , wherein the carbon-based sorbent material comprises one or more of:
a pyrolyzed polymer or a polysaccharide; and/or an activated carbon, a carbon nitride, a graphitic carbon nitride, a graphite and a carbon molecular sieve.

20 . The radionuclide separating system according to claim 16 , wherein the carbon-based sorbent material is shaped in beads or
wherein the carbon-based sorbent material is provided as shell of beads, as a tubular structures, as honeycomb or as 3D printed monolith.

21 . The radionuclide separating system according to claim 16 , wherein the carbon-based sorbent material is shaped in beads having a size between 5 μm and 1 mm.

22 . The radionuclide separating system according to claim 16 , wherein the surface area of the sorbent material is smaller than 100 m 2 /g.

23 . The radionuclide separating system according to claim 16 , wherein the H/C molar ratio of the carbon-based sorbent material is lower than 1.

24 . The radionuclide separating system according to claim 16 , wherein the radionuclide separating system is a direct radionuclide separating system, the carbon-based sorbent material having a strong affinity for both the 225 Ac parent radionuclide and the daughter radionuclide, so as to selectively desorb the daughter radionuclide.

25 . The radionuclide separating system according to claim 16 , wherein the radionuclide separating system is an inverse radionuclide separating system, the carbon-based sorbent material being adapted for having a higher affinity for the daughter radionuclide rather than to the 225 Ac parent radionuclide.

26 . The radionuclide separating system according to claim 25 , wherein the carbon-based sorbent material comprises one or more of a phosphate group, carbonyl, a hydroxyl group or a carboxylic acid.

27 . A method for separating radionuclides, the method comprising:
loading a mixture of a 225 Ac parent radionuclide and a 213 Bi daughter radionuclide to a column comprising a carbon-based sorbent material, allowing the sorbent material to selectively interact with the 225 Ac parent radionuclide and the 213 Bi daughter radionuclide, the sorbent material having affinity for interacting with the 225 Ac parent radionuclide and 213 Bi daughter radionuclide so as to allow selective desorption of the 225 Ac parent radionuclide and the 213 Bi daughter radionuclide, and selectively desorbing the 225 Ac parent radionuclide and the 213 Bi daughter radionuclide after said interaction, so as to selectively obtain the 213 Bi daughter radionuclide.

28 . The method according to claim 27 , wherein the sorbent material is adapted so that the sorbent material has a higher affinity for the 225 Ac parent radionuclide than the 213 Bi daughter radionuclide so as to bind the 225 Ac parent radionuclide,
wherein said selectively obtaining the daughter radionuclide comprises, eluting the 213 Bi daughter radionuclide from the column using an eluent having a pH of at least 1 after the 225 Ac parent radionuclide was bound to the sorbent material.

29 . The method according to claim 27 , wherein the sorbent material is adapted so that the sorbent material has a higher affinity for the 213 Bi daughter radionuclide than the 225 Ac parent radionuclide so as to bind the 213 Bi daughter radionuclide,
wherein said selectively obtaining the 213 Bi daughter radionuclide comprises rinsing the column, and thereafter stripping the 213 Bi daughter radionuclide from the column into a strip solution.

30 . The method according to claim 29 , wherein the strip solution is further added to a second column having a sorbent material with higher affinity for the 225 Ac parent radionuclide than for the 213 Bi daughter radionuclide and eluting the 213 Bi daughter radionuclide from the second column, after interaction between the sorbent material of the second column and remaining 225 Ac parent radionuclide in the strip solution was allowed.

Assignees

• Sck Cen
• Vito Nv
• Univ Leuven Kath

Inventors

• Zhu hongshan
• Heinitz Stephan
• Mullens Steven
• Binnemans Koen
• Cardinaels Thomas

Classifications

• G21G1/001 Primary

  Recovery of specific isotopes from irradiated targets · CPC title

• C22B3/24

  by adsorption on solid substances, e.g. by extraction with solid resins · CPC title

• C22B30/06 Primary

  Obtaining bismuth · CPC title

• C22B3/42

  by ion-exchange extraction · CPC title