skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Bulk production and evaluation of high specific activity 186g Re for cancer therapy using enriched 186 WO 3 targets in a proton beam

Abstract

Rhenium-186 g (t 1/2 = 3.72 d) is a β– emitting isotope suitable for theranostic applications. Current production methods rely on reactor production by way of the reaction 185Re(n,γ) 186gRe, which results in low specific activities limiting its use for cancer therapy. Production via charged particle activation of enriched 186W results in a 186gRe product with a much specific activity, allowing it to be used more broadly for targeted radiotherapy applications. Furthermore, this targets the unmet clinical need for more efficient radiotherapeutics.

Authors:
; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Nuclear Physics (NP) (SC-26)
OSTI Identifier:
1415249
Alternate Identifier(s):
OSTI ID: 1345946
Report Number(s):
LA-UR-16-29352
Journal ID: ISSN 0969-8051; TRN: US1700520
Grant/Contract Number:
AC52-06NA25396; FOA-0000048
Resource Type:
Journal Article: Publisher's Accepted Manuscript
Journal Name:
Nuclear Medicine and Biology
Additional Journal Information:
Journal Volume: 49; Journal Issue: C; Journal ID: ISSN 0969-8051
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
62 RADIOLOGY AND NUCLEAR MEDICINE; Inorganic and Physical Chemistry

Citation Formats

Mastren, Tara, Radchenko, Valery, Bach, Hong T., Balkin, Ethan R., Birnbaum, Eva R., Brugh, Mark, Engle, Jonathan W., Gott, Matthew D., Guthrie, James, Hennkens, Heather M., John, Kevin D., Ketring, Alan R., Kuchuk, Marina, Maassen, Joel R., Naranjo, Cleo M., Nortier, F. Meiring, Phelps, Tim E., Jurisson, Silvia S., Wilbur, D. Scott, and Fassbender, Michael E. Bulk production and evaluation of high specific activity 186g Re for cancer therapy using enriched 186 WO 3 targets in a proton beam. United States: N. p., 2017. Web. doi:10.1016/j.nucmedbio.2017.02.006.
Mastren, Tara, Radchenko, Valery, Bach, Hong T., Balkin, Ethan R., Birnbaum, Eva R., Brugh, Mark, Engle, Jonathan W., Gott, Matthew D., Guthrie, James, Hennkens, Heather M., John, Kevin D., Ketring, Alan R., Kuchuk, Marina, Maassen, Joel R., Naranjo, Cleo M., Nortier, F. Meiring, Phelps, Tim E., Jurisson, Silvia S., Wilbur, D. Scott, & Fassbender, Michael E. Bulk production and evaluation of high specific activity 186g Re for cancer therapy using enriched 186 WO 3 targets in a proton beam. United States. doi:10.1016/j.nucmedbio.2017.02.006.
Mastren, Tara, Radchenko, Valery, Bach, Hong T., Balkin, Ethan R., Birnbaum, Eva R., Brugh, Mark, Engle, Jonathan W., Gott, Matthew D., Guthrie, James, Hennkens, Heather M., John, Kevin D., Ketring, Alan R., Kuchuk, Marina, Maassen, Joel R., Naranjo, Cleo M., Nortier, F. Meiring, Phelps, Tim E., Jurisson, Silvia S., Wilbur, D. Scott, and Fassbender, Michael E. Thu . "Bulk production and evaluation of high specific activity 186g Re for cancer therapy using enriched 186 WO 3 targets in a proton beam". United States. doi:10.1016/j.nucmedbio.2017.02.006.
@article{osti_1415249,
title = {Bulk production and evaluation of high specific activity 186g Re for cancer therapy using enriched 186 WO 3 targets in a proton beam},
author = {Mastren, Tara and Radchenko, Valery and Bach, Hong T. and Balkin, Ethan R. and Birnbaum, Eva R. and Brugh, Mark and Engle, Jonathan W. and Gott, Matthew D. and Guthrie, James and Hennkens, Heather M. and John, Kevin D. and Ketring, Alan R. and Kuchuk, Marina and Maassen, Joel R. and Naranjo, Cleo M. and Nortier, F. Meiring and Phelps, Tim E. and Jurisson, Silvia S. and Wilbur, D. Scott and Fassbender, Michael E.},
abstractNote = {Rhenium-186 g (t1/2 = 3.72 d) is a β– emitting isotope suitable for theranostic applications. Current production methods rely on reactor production by way of the reaction 185Re(n,γ)186gRe, which results in low specific activities limiting its use for cancer therapy. Production via charged particle activation of enriched 186W results in a 186gRe product with a much specific activity, allowing it to be used more broadly for targeted radiotherapy applications. Furthermore, this targets the unmet clinical need for more efficient radiotherapeutics.},
doi = {10.1016/j.nucmedbio.2017.02.006},
journal = {Nuclear Medicine and Biology},
number = C,
volume = 49,
place = {United States},
year = {Thu Jun 01 00:00:00 EDT 2017},
month = {Thu Jun 01 00:00:00 EDT 2017}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record at 10.1016/j.nucmedbio.2017.02.006

Citation Metrics:
Cited by: 3works
Citation information provided by
Web of Science

Save / Share:
  • Rhenium-186 g (t 1/2 = 3.72 d) is a β– emitting isotope suitable for theranostic applications. Current production methods rely on reactor production by way of the reaction 185Re(n,γ) 186gRe, which results in low specific activities limiting its use for cancer therapy. Production via charged particle activation of enriched 186W results in a 186gRe product with a much specific activity, allowing it to be used more broadly for targeted radiotherapy applications. Furthermore, this targets the unmet clinical need for more efficient radiotherapeutics.
  • This investigation evaluated target fabrication and beam parameters for scale-up production of high specific activity 186Re using deuteron irradiation of enriched 186W via the 186W(d,2n) 186Re reaction. Thick W and WO 3 targets were prepared, characterized and evaluated in deuteron irradiations. Full-thickness targets, as determined using SRIM, were prepared by uniaxi-ally pressing powdered natural abundance W and WO 3, or 96.86% enriched 186W, into Al target supports. Alternatively, thick targets were prepared by pressing 186W between two layers of graphite powder or by placing pre-sintered (1105°C, 12 hours) natural abundance WO 3 pellets into an Al target support. Assessments ofmore » structural integrity were made on each target pre-pared. Prior to irradiation, material composition analyses were conducted using SEM, XRD, and Raman spectroscopy. With-in a minimum of 24 hours post irradiation, gamma-ray spectroscopy was performed on all targets to assess production yields and radionuclidic byproducts. Problems were encountered with the structural integrity of some pressed W and WO 3 pellets before and during irradiation, and target material characterization results could be correlated with the structural integrity of the pressed target pellets. Under the conditions studied, the findings suggest that all WO 3 targets prepared and studied were unacceptable. By contrast, 186W metal was found to be a viable target material for 186Re production. Lastly, thick targets prepared with powdered 186W pressed between layers of graphite provided a particularly robust target configuration.« less
  • Production of high specific activity 186gRe is of interest for development of theranostic radiopharmaceuticals. Previous studies have shown that high specific activity 186gRe can be obtained by cyclotron irradiation of enriched 186W via the 186W(d,2n) 186gRe reaction, but most irradiations were conducted at low beam currents and for short durations. In this paper, enriched 186W metal targets were irradiated at high incident deuteron beam currents to demonstrate production rates and contaminants produced when using thick targets. Full-stopping thick targets, as determined using SRIM, were prepared by uniaxial pressing of powdered natural abundance W metal or 96.86% enriched 186W metal encasedmore » between two layers of graphite flakes for target material stabilization. An assessment of structural integrity was made on each target preparation. To assess the performance of graphite-encased thick 186W metal targets, along with the impact of encasing on the separation chemistry, targets were first irradiated using a 22 MeV deuteron beam for 10 min at 10, 20, and 27 μA, with an estimated nominal deuteron energy of 18.7 MeV on the 186W target material (after energy degradation correction from top graphite layer). Gamma-ray spectrometry was performed post EOB on all targets to assess production yields and radionuclidic byproducts. The investigation also evaluated a method to recover and recycle enriched target material from a column isolation procedure. Material composition analyses of target materials, pass-through/wash solutions and recycling process isolates were conducted with SEM, FTIR, XRD, EDS and ICP-MS spectrometry. Finally, to demonstrate scaled-up production, a graphite-encased 186W target made from recycled 186W was irradiated for ~2 h with 18.7 MeV deuterons at a beam current of 27 μA to provide 0.90 GBq (24.3 mCi) of 186gRe, decay-corrected to the end of bombardment. ICP-MS analysis of the isolated 186gRe solution provided data that indicated the specific activity of 186gRe in this scaled-up production run was 2.6±0.5 GBq/μg (70±10 Ci/mg).« less