US 12,451,264 B2
Methods for extracting radioisotopes from radiologically contaminated waste
Steven Haun, Kingsport, TN (US); Paul Sylvester, Denver, CO (US); Timothy Nicholas Milner, Lexington, SC (US); and Colin Russell Austin, Port Charlotte, FL (US)
Filed by EnergySolutions, LLC, Salt Lake City, UT (US)
Filed on Feb. 20, 2025, as Appl. No. 19/058,667.
Application 19/058,667 is a continuation in part of application No. PCT/US2024/042804, filed on Aug. 16, 2024.
Claims priority of provisional application 63/519,961, filed on Aug. 16, 2023.
Prior Publication US 2025/0232889 A1, Jul. 17, 2025
Int. Cl. G21F 9/30 (2006.01); B01D 53/14 (2006.01); B01D 53/62 (2006.01); B01D 53/78 (2006.01); B01D 53/80 (2006.01); B01D 53/81 (2006.01)
CPC G21F 9/30 (2013.01) [B01D 53/1475 (2013.01); B01D 53/1493 (2013.01); B01D 53/62 (2013.01); B01D 53/78 (2013.01); B01D 53/80 (2013.01); B01D 53/81 (2013.01); B01D 2251/304 (2013.01); B01D 2251/404 (2013.01); B01D 2251/408 (2013.01); B01D 2251/604 (2013.01); B01D 2257/504 (2013.01)] 20 Claims
OG exemplary drawing
 
1. A method of separating radioisotopes from ion exchange resin used to process nuclear waste, the method comprising:
contacting the ion exchange resin with an aqueous solution including a salt or acid; and
separating the aqueous solution from the ion exchange resin to form an enriched solution;
wherein the enriched solution includes at least 80% of the activity of at least one of the radioisotopes in the ion exchange resin.
 
11. A method of separating radioisotopes from ion exchange resin used to process nuclear waste, the method comprising:
contacting the ion exchange resin with an aqueous salt solution; and
separating the aqueous salt solution from the ion exchange resin to form an enriched solution;
wherein the enriched solution includes at least 80% of the activity of Sr-90, Co-60, Ni-63, Cs-137, C-14, Co-58, and/or Mn-54 radioisotopes in the ion exchange resin.