2016
DOI: 10.1016/j.nucmedbio.2015.09.007
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Improved production and processing of 89Zr using a solution target

Abstract: The BMLT-2 target allowed doubling of the beam current for production of (89)Zr, resulting in a greater than 2-fold increase in production yield in comparison with a conventional liquid target. The new one-pot synthesis of hydroxamate resin provides a simpler synthesis method for the (89)Zr trapping resin. Finally, phosphate buffer elutes the (89)Zrfrom the hydroxamate resin in high efficiency while at the same time providing a more biocompatible medium for subsequent use of (89)Zr.

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Cited by 31 publications
(28 citation statements)
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“…Oehlke et al also irradiated solutions of dissolved yttrium nitrate with similar concentrations to produce 89 Zr (Oehlke et al 2015). Their lower 7,3 μA target current and proton energy of 12 MeV protons explained the lower activities produced and the reduced production yield at saturation, showing agreement with the results from Pandey et al (Pandey et al 2016) (Table 4). In all cases, the proton energy was chosen to avoid the production of the undesirable long-lived 88 Zr (t 1/2 = 83,4 days).…”
Section: Zrsupporting
confidence: 66%
See 1 more Smart Citation
“…Oehlke et al also irradiated solutions of dissolved yttrium nitrate with similar concentrations to produce 89 Zr (Oehlke et al 2015). Their lower 7,3 μA target current and proton energy of 12 MeV protons explained the lower activities produced and the reduced production yield at saturation, showing agreement with the results from Pandey et al (Pandey et al 2016) (Table 4). In all cases, the proton energy was chosen to avoid the production of the undesirable long-lived 88 Zr (t 1/2 = 83,4 days).…”
Section: Zrsupporting
confidence: 66%
“…The improved process they developed enabled the production of 349 MBq of 89 Zr by irradiating a target solution composed of a 2 M solution of yttrium nitrate dissolved in 1, 25 M nitric acid with 40 μA of 14 MeV protons for 2 h (Pandey et al 2016). Oehlke et al also irradiated solutions of dissolved yttrium nitrate with similar concentrations to produce 89 Zr (Oehlke et al 2015).…”
Section: Zrmentioning
confidence: 99%
“…Its production in moderate (100s of MBq) quantities through the 89 Y(p,n) 89 Zr nuclear reaction (Saha et al, 1966) is currently feasible using small medical cyclotrons capable of irradiating yttrium targets with 5 – 20 μA of 10 – 20 MeV protons. A variety of cyclotron targetry methods have been investigated including the irradiation of Y foils (Link et al, 1986 and DeJesus and Nickles, 1990), Y-sputtered copper (Meijs et al, 1994), powdered Y (Nagatsu et al, 2012), sedimented Y 2 O 3 (Sadeghi et al, 2010), and aqueous solutions of Y(NO 3 ) 3 (Pandey et al, 2016). However, as clinical trials requiring 40 – 200 MBq per human dose of 89 Zr-labeled compound continue to expand, the need for methods of producing GBq quantities of 89 Zr is increasing.…”
Section: Introductionmentioning
confidence: 99%
“…The quantity of zinc necessary for the target need to be removed as it and all other metal impurities may perturb the radiolabeling reaction of gallium-68. Intense research on this topic lead to several purification methods based on solvent extraction [34,35], precipitation [36] and solid phase separation [37][38][39][40][41][42][43][44] and suitable for automation.…”
Section: Work In Progress: Cyclotronmentioning
confidence: 99%