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Title: An automated flow system incorporating in-line acid dissolution of bismuth metal from a cyclotron irradiated target assembly for use in the isolation of astatine-211

Authors:
; ; ; ; ; ; ;
Publication Date:
Sponsoring Org.:
USDOE Office of Science (SC), Nuclear Physics (NP) (SC-26)
OSTI Identifier:
1412941
Grant/Contract Number:
AC05-76RL01830; FWP 63816
Resource Type:
Journal Article: Publisher's Accepted Manuscript
Journal Name:
Applied Radiation and Isotopes
Additional Journal Information:
Journal Volume: 122; Journal Issue: C; Related Information: CHORUS Timestamp: 2017-12-11 02:52:28; Journal ID: ISSN 0969-8043
Publisher:
Elsevier
Country of Publication:
United Kingdom
Language:
English

Citation Formats

O’Hara, Matthew J., Krzysko, Anthony J., Niver, Cynthia M., Morrison, Samuel S., Owsley, Jr., Stanley L., Hamlin, Donald K., Dorman, Eric F., and Scott Wilbur, D.. An automated flow system incorporating in-line acid dissolution of bismuth metal from a cyclotron irradiated target assembly for use in the isolation of astatine-211. United Kingdom: N. p., 2017. Web. doi:10.1016/j.apradiso.2017.02.001.
O’Hara, Matthew J., Krzysko, Anthony J., Niver, Cynthia M., Morrison, Samuel S., Owsley, Jr., Stanley L., Hamlin, Donald K., Dorman, Eric F., & Scott Wilbur, D.. An automated flow system incorporating in-line acid dissolution of bismuth metal from a cyclotron irradiated target assembly for use in the isolation of astatine-211. United Kingdom. doi:10.1016/j.apradiso.2017.02.001.
O’Hara, Matthew J., Krzysko, Anthony J., Niver, Cynthia M., Morrison, Samuel S., Owsley, Jr., Stanley L., Hamlin, Donald K., Dorman, Eric F., and Scott Wilbur, D.. Sat . "An automated flow system incorporating in-line acid dissolution of bismuth metal from a cyclotron irradiated target assembly for use in the isolation of astatine-211". United Kingdom. doi:10.1016/j.apradiso.2017.02.001.
@article{osti_1412941,
title = {An automated flow system incorporating in-line acid dissolution of bismuth metal from a cyclotron irradiated target assembly for use in the isolation of astatine-211},
author = {O’Hara, Matthew J. and Krzysko, Anthony J. and Niver, Cynthia M. and Morrison, Samuel S. and Owsley, Jr., Stanley L. and Hamlin, Donald K. and Dorman, Eric F. and Scott Wilbur, D.},
abstractNote = {},
doi = {10.1016/j.apradiso.2017.02.001},
journal = {Applied Radiation and Isotopes},
number = C,
volume = 122,
place = {United Kingdom},
year = {Sat Apr 01 00:00:00 EDT 2017},
month = {Sat Apr 01 00:00:00 EDT 2017}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record at 10.1016/j.apradiso.2017.02.001

Citation Metrics:
Cited by: 1work
Citation information provided by
Web of Science

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  • Astatine-211 (211At) is a promising cyclotron-produced radionuclide being investigated for use in targeted alpha therapy of blood borne and metastatic cancers, as well as treatment of tumor remnants after surgical resections. The isolation of trace quantities of 211At, produced within several grams of a Bi metal cyclotron target, involves a complex, multi-step procedure: (1) Bi metal dissolution in strong HNO3, (2) distillation of the HNO3 to yield Bi salts containing 211At, (3) dissolution of the salts in strong HCl, (4) solvent extraction of 211At from bismuth salts with diisopropyl ether (DIPE), and (5) back-extraction of 211At from DIPE into NaOH,more » leading to a purified 211At product. Step (1) has been addressed first to begin the process of automating the onerous 211At isolation process. A computer-controlled Bi target dissolution system has been designed. The system performs in-line dissolution of Bi metal from the target assembly using an enclosed target dissolution block, routing the resulting solubilized 211At/Bi mixture to the subsequent process step. The primary parameters involved in Bi metal solubilization (HNO3 concentration and influent flow rate) were optimized prior to evaluation of the system performance on replicate cyclotron irradiated targets. The results indicate that the system performs reproducibly, having nearly quantitative release of 211At from irradiated targets, with cumulative 211At recoveries that follow a sigmoidal function. The predictable nature of the 211At release profile allows the user to tune the system to meet target processing requirements.« less
  • Zirconium-89 (89Zr), produced by the (p,n) reaction from naturally monoisotopic yttrium (natY), is a promising positron emitting isotope for immunoPET imaging. Its long half-life of 78.4 h is sufficient for evaluating slow physiological processes. A prototype automated fluidic system, coupled to on-line and in-line detectors, has been constructed to facilitate development of new 89Zr purification methodologies. The highly reproducible reagent delivery platform and near-real time monitoring of column effluents allows for efficient method optimization. The separation of Zr from dissolved Y metal targets was evaluated using several anion exchange resins. Each resin was evaluated against its ability to quantitatively capturemore » Zr from a load solution that is high in dissolved Y. The most appropriate anion exchange resin for this application was identified, and the separation method was optimized. The method is capable of a high Y decontamination factor (>105) and has been shown to separate Fe, an abundant contaminant in Y foils, from the 89Zr elution fraction. Finally, the performance of the method was evaluated using cyclotron bombarded Y foil targets. The separation method was shown to achieve >95% recovery of the 89Zr present in the foils. The 89Zr eluent, however, was in a chemical matrix not immediately conducive to labeling onto proteins. The main intent of this study was to develop a tandem column 89Zr purification process, wherein the anion exchange column method described here is the first separation in a dual-column purification process.« less
  • Zirconium-89 ( 89Zr), produced by the (p, n) reaction from naturally monoisotopic yttrium ( natY), is a promising positron emitting isotope for immunoPET imaging. Its long half-life of 78.4 h is sufficient for evaluating slow physiological processes. A prototype automated fluidic system, coupled to on-line and in-line detectors, has been constructed to facilitate development of new 89Zr purification methodologies. The highly reproducible reagent delivery platform and near-real time monitoring of column effluents allows for efficient method optimization. The separation of Zr from dissolved Y metal targets was evaluated using several anion exchange resins. Each resin was evaluated against its abilitymore » to quantitatively capture Zr from a load solution high in dissolved Y. The most appropriate anion exchange resin for this application was identified, and the separation method was optimized. The method is capable of a high Y decontamination factor (>10 5) and has been shown to remove Fe, an abundant contaminant in Y foils, from the 89Zr elution fraction. Finally, the method was evaluated using cyclotron bombarded Y foil targets; the method was shown to achieve >95% recovery of the 89Zr present in the foils. The anion exchange column method described here is intended to be the first 89Zr isolation stage in a dual-column purification process.« less