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Title: Deuteron irradiation of W and WO3 for production of high specific activity 186Re: Challenges associated with thick target preparation

Journal Article · · Applied Radiation and Isotopes
 [1];  [2];  [3];  [4];  [1];  [1];  [3];  [5];  [6];  [7];  [8];  [1]
  1. Univ. of Washington, Seattle, WA (United States). Dept. of Radiation Oncology
  2. Univ. of Washington, Seattle, WA (United States). Dept. of Radiation Oncology; Univ. of Alberta, Edmonton, AB (Canada). Cross Cancer Inst., Dept. of Oncology
  3. Univ. of Washington, Seattle, WA (United States). Dept. of Materials Science and Engineering
  4. Univ. of Washington, Seattle, WA (United States). Dept. of Chemistry
  5. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  6. Brookhaven National Lab. (BNL), Upton, NY (United States). Collider-Accelerator Dept.; Univ. of Missouri Research Reactor Center, Columbia, MO (United States)
  7. Univ. of Missouri Research Reactor Center, Columbia, MO (United States)
  8. Univ. of Missouri, Columbia, MO (United States). of Chemistry

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 WO3 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 WO3, 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 WO3 pellets into an Al target support. Assessments of 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 WO3 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 WO3 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.

Research Organization:
Brookhaven National Laboratory (BNL), Upton, NY (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Nuclear Physics (NP)
Grant/Contract Number:
SC0012704; SC0007348
OSTI ID:
1338598
Alternate ID(s):
OSTI ID: 1358798
Report Number(s):
BNL-113242-2016-JA; R&D Project: KBCH139; KB0202011; TRN: US1701816
Journal Information:
Applied Radiation and Isotopes, Vol. 115, Issue C; ISSN 0969-8043
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 14 works
Citation information provided by
Web of Science

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