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The production and separation of 161 Tb with high specific activity at the University of Utah
Targeted radiotherapy (TRT) is an increasingly prominent area of research in nuclear medicine, particularly in the context of treating cancerous tumors. One radionuclide of considerable interest for TRT is terbium-161 (t = 6.95 days), which undergoes beta emission and shares similar decay propertie...
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Published in: | Applied radiation and isotopes 2024-12, Vol.214, p.111530 |
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description | Targeted radiotherapy (TRT) is an increasingly prominent area of research in nuclear medicine, particularly in the context of treating cancerous tumors. One radionuclide of considerable interest for TRT is terbium-161 (t
= 6.95 days), which undergoes beta emission and shares similar decay properties as
Lu (FDA-approved as LUTATHERA® and PLUVICTO®). Besides beta emission,
Tb also emits a significant number of conversion and Auger electrons further enhancing its therapeutic potential. Terbium-161 can be produced using nuclear reactors through an indirect neutron capture reaction, G64160dn,γG64161d→3.66min,β
T65161b, from
Gd targets. However, a key challenge in utilizing
Tb for TRT lies in effectively separating target and product materials to attain high specific activity for radiolabeling. Here, we detail the production of no-carrier added
Tb using low flux research reactors (mean thermal ( |
format | article |
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= 6.95 days), which undergoes beta emission and shares similar decay properties as
Lu (FDA-approved as LUTATHERA® and PLUVICTO®). Besides beta emission,
Tb also emits a significant number of conversion and Auger electrons further enhancing its therapeutic potential. Terbium-161 can be produced using nuclear reactors through an indirect neutron capture reaction, G64160dn,γG64161d→3.66min,β
T65161b, from
Gd targets. However, a key challenge in utilizing
Tb for TRT lies in effectively separating target and product materials to attain high specific activity for radiolabeling. Here, we detail the production of no-carrier added
Tb using low flux research reactors (mean thermal (<0.625 eV) neutron flux: 1.356×10
n∙cm
∙s
) like the University of Utah TRIGA Reactor, using enriched
Gd
O
targets (1.5 ± 0.3 μCi of
Tb per mg of
Gd target per hour of irradiation). We also developed a separation technique based on cation exchange and extraction chromatography, suitable for mCi level irradiations with targets exceeding 200 mg. In a simulated full-scale irradiation,
Tb was successfully isolated from large mass targets using cation exchange (AG 50W-X8, with 2-hydroxyisobutyric acid at 70 mM, pH 4.75) and extraction chromatography (LN Resin, 0.5-0.75 M HNO
) methods. This resulted in high apparent molar activities of [
Tb]Tb-DOTA (113 ± 3 MBq/nmol), demonstrating high purity
Tb relevant for potential future preclinical applications.</description><identifier>EISSN: 1872-9800</identifier><identifier>PMID: 39342764</identifier><language>eng</language><publisher>England</publisher><subject>Nuclear Reactors ; Radiopharmaceuticals - isolation & purification ; Terbium - chemistry ; Utah</subject><ispartof>Applied radiation and isotopes, 2024-12, Vol.214, p.111530</ispartof><rights>Copyright © 2024 Elsevier Ltd. All rights reserved.</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784</link.rule.ids><backlink>$$Uhttps://www.ncbi.nlm.nih.gov/pubmed/39342764$$D View this record in MEDLINE/PubMed$$Hfree_for_read</backlink></links><search><creatorcontrib>Holiski, Connor K</creatorcontrib><creatorcontrib>Bender, Aidan A</creatorcontrib><creatorcontrib>Monte, Peñafrancia F</creatorcontrib><creatorcontrib>Hennkens, Heather M</creatorcontrib><creatorcontrib>Embree, Mary F</creatorcontrib><creatorcontrib>Wang, Meng-Jen Vince</creatorcontrib><creatorcontrib>Sjoden, Glenn E</creatorcontrib><creatorcontrib>Mastren, Tara</creatorcontrib><title>The production and separation of 161 Tb with high specific activity at the University of Utah</title><title>Applied radiation and isotopes</title><addtitle>Appl Radiat Isot</addtitle><description>Targeted radiotherapy (TRT) is an increasingly prominent area of research in nuclear medicine, particularly in the context of treating cancerous tumors. One radionuclide of considerable interest for TRT is terbium-161 (t
= 6.95 days), which undergoes beta emission and shares similar decay properties as
Lu (FDA-approved as LUTATHERA® and PLUVICTO®). Besides beta emission,
Tb also emits a significant number of conversion and Auger electrons further enhancing its therapeutic potential. Terbium-161 can be produced using nuclear reactors through an indirect neutron capture reaction, G64160dn,γG64161d→3.66min,β
T65161b, from
Gd targets. However, a key challenge in utilizing
Tb for TRT lies in effectively separating target and product materials to attain high specific activity for radiolabeling. Here, we detail the production of no-carrier added
Tb using low flux research reactors (mean thermal (<0.625 eV) neutron flux: 1.356×10
n∙cm
∙s
) like the University of Utah TRIGA Reactor, using enriched
Gd
O
targets (1.5 ± 0.3 μCi of
Tb per mg of
Gd target per hour of irradiation). We also developed a separation technique based on cation exchange and extraction chromatography, suitable for mCi level irradiations with targets exceeding 200 mg. In a simulated full-scale irradiation,
Tb was successfully isolated from large mass targets using cation exchange (AG 50W-X8, with 2-hydroxyisobutyric acid at 70 mM, pH 4.75) and extraction chromatography (LN Resin, 0.5-0.75 M HNO
) methods. This resulted in high apparent molar activities of [
Tb]Tb-DOTA (113 ± 3 MBq/nmol), demonstrating high purity
Tb relevant for potential future preclinical applications.</description><subject>Nuclear Reactors</subject><subject>Radiopharmaceuticals - isolation & purification</subject><subject>Terbium - chemistry</subject><subject>Utah</subject><issn>1872-9800</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2024</creationdate><recordtype>article</recordtype><recordid>eNqFjtsKgkAYhJcg0g6vEP8LCOsBD9dR9AB6GfGra_tH6rK7Gr59FnXd1TDDfMMsmOunSeBlKecOWxtz55xHaRasmBNmYRQkceSySy4FKN3XQ2Wp7wC7GoxQqPFj-wb82Ie8hCdZCZJuEowSFTVUAc7ISHYCtGDnmaKjUWjzTmausCi3bNngw4jdVzdsfzrmh7OnhrIV9VVpalFP19-f8G_hBc_yQEs</recordid><startdate>202412</startdate><enddate>202412</enddate><creator>Holiski, Connor K</creator><creator>Bender, Aidan A</creator><creator>Monte, Peñafrancia F</creator><creator>Hennkens, Heather M</creator><creator>Embree, Mary F</creator><creator>Wang, Meng-Jen Vince</creator><creator>Sjoden, Glenn E</creator><creator>Mastren, Tara</creator><scope>CGR</scope><scope>CUY</scope><scope>CVF</scope><scope>ECM</scope><scope>EIF</scope><scope>NPM</scope></search><sort><creationdate>202412</creationdate><title>The production and separation of 161 Tb with high specific activity at the University of Utah</title><author>Holiski, Connor K ; Bender, Aidan A ; Monte, Peñafrancia F ; Hennkens, Heather M ; Embree, Mary F ; Wang, Meng-Jen Vince ; Sjoden, Glenn E ; Mastren, Tara</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-pubmed_primary_393427643</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2024</creationdate><topic>Nuclear Reactors</topic><topic>Radiopharmaceuticals - isolation & purification</topic><topic>Terbium - chemistry</topic><topic>Utah</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Holiski, Connor K</creatorcontrib><creatorcontrib>Bender, Aidan A</creatorcontrib><creatorcontrib>Monte, Peñafrancia F</creatorcontrib><creatorcontrib>Hennkens, Heather M</creatorcontrib><creatorcontrib>Embree, Mary F</creatorcontrib><creatorcontrib>Wang, Meng-Jen Vince</creatorcontrib><creatorcontrib>Sjoden, Glenn E</creatorcontrib><creatorcontrib>Mastren, Tara</creatorcontrib><collection>Medline</collection><collection>MEDLINE</collection><collection>MEDLINE (Ovid)</collection><collection>MEDLINE</collection><collection>MEDLINE</collection><collection>PubMed</collection><jtitle>Applied radiation and isotopes</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Holiski, Connor K</au><au>Bender, Aidan A</au><au>Monte, Peñafrancia F</au><au>Hennkens, Heather M</au><au>Embree, Mary F</au><au>Wang, Meng-Jen Vince</au><au>Sjoden, Glenn E</au><au>Mastren, Tara</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>The production and separation of 161 Tb with high specific activity at the University of Utah</atitle><jtitle>Applied radiation and isotopes</jtitle><addtitle>Appl Radiat Isot</addtitle><date>2024-12</date><risdate>2024</risdate><volume>214</volume><spage>111530</spage><pages>111530-</pages><eissn>1872-9800</eissn><abstract>Targeted radiotherapy (TRT) is an increasingly prominent area of research in nuclear medicine, particularly in the context of treating cancerous tumors. One radionuclide of considerable interest for TRT is terbium-161 (t
= 6.95 days), which undergoes beta emission and shares similar decay properties as
Lu (FDA-approved as LUTATHERA® and PLUVICTO®). Besides beta emission,
Tb also emits a significant number of conversion and Auger electrons further enhancing its therapeutic potential. Terbium-161 can be produced using nuclear reactors through an indirect neutron capture reaction, G64160dn,γG64161d→3.66min,β
T65161b, from
Gd targets. However, a key challenge in utilizing
Tb for TRT lies in effectively separating target and product materials to attain high specific activity for radiolabeling. Here, we detail the production of no-carrier added
Tb using low flux research reactors (mean thermal (<0.625 eV) neutron flux: 1.356×10
n∙cm
∙s
) like the University of Utah TRIGA Reactor, using enriched
Gd
O
targets (1.5 ± 0.3 μCi of
Tb per mg of
Gd target per hour of irradiation). We also developed a separation technique based on cation exchange and extraction chromatography, suitable for mCi level irradiations with targets exceeding 200 mg. In a simulated full-scale irradiation,
Tb was successfully isolated from large mass targets using cation exchange (AG 50W-X8, with 2-hydroxyisobutyric acid at 70 mM, pH 4.75) and extraction chromatography (LN Resin, 0.5-0.75 M HNO
) methods. This resulted in high apparent molar activities of [
Tb]Tb-DOTA (113 ± 3 MBq/nmol), demonstrating high purity
Tb relevant for potential future preclinical applications.</abstract><cop>England</cop><pmid>39342764</pmid></addata></record> |
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language | eng |
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source | ScienceDirect Journals |
subjects | Nuclear Reactors Radiopharmaceuticals - isolation & purification Terbium - chemistry Utah |
title | The production and separation of 161 Tb with high specific activity at the University of Utah |
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