Ff. Knapp et al., PROCESSING OF REACTOR-PRODUCED W-188 FOR FABRICATION OF CLINICAL-SCALE ALUMINA-BASED W-188 RE-188 GENERATORS/, Applied radiation and isotopes, 45(12), 1994, pp. 1123-1128
Citations number
24
Categorie Soggetti
Nuclear Sciences & Tecnology","Radiology,Nuclear Medicine & Medical Imaging
The traditional technique for processing of reactor-irradiated W-186-e
nriched tungsten oxide (WO3) targets involves formation of W-188-sodiu
m tungstate solutions by target dissolution in 0.1 M NaOH. Following l
ong irradiations (>21 days) in the ORNL High Flux Isotope Reactor (HFI
R) the (WO3)-W-186 targets contain a NaOH-insoluble W-188-labeled blac
k solid (approx. 30-50% of total activity) which decreases the yield a
nd specific activity of the processed W-188 (e.g. 5-6 mCi/mg W-186 for
a 79-day irradiation). The black material is postulated to represent
a ''tungsten blue'' insoluble polymeric form of tungsten oxide, which
we have now found to dissolve in 0.1 M NaOH containing 5% sodium hypoc
hlorite solution. Complete dissolution results in a significant increa
se in the yield and specific activity of sodium W-188-tungstate. As an
alternative approach, irradiated W-186-enriched metal targets dissolv
e in sodium hydroxide solution by cautious addition of <30% hydrogen p
eroxide. Sodium W-188-tungstate solutions prepared from processing of
such metal targets show no evidence of residual black insoluble materi
al. Specific activity values for completely dissolved HFIR-irradiated
W-186 targets have increased to 10 mCi/mg (43.5 days) and 12.9 mCi/mg
(49.2 days). Large clinical scale (>1 Ci) generators prepared from hyp
ochlorite-processed W-186 oxide or peroxide-processed W-186 metal targ
ets exhibit the expected Re-188 high yield and low W-188 breakthrough.