Production and radiochemical separation of 147Gd

Production of 177Lu for Targeted Radionuclide Therapy: Available Options

“…The transfer of 177 Lu out of the thermodynamically very stable 177 Lu-α-HIBA species prior to labeling constitutes a necessity as its presence not only leads to poor labeling yield, but also requires post-labeling purification. In an attempt to circumvent this drawback, one of the methods used for the removal of α-HIBA is the adsorption on a cation exchanger followed by elution with~9 M HCl [61]. Use of e t h y l e n e -d i a m i n e -t e t r a -a c e t a t e o r 1 , 2 -d i a m i n ocyclohexanetetraacetate (α=1.7) in lieu of α-HIBA met with limited success because of solubility problems and the requirement of additional steps to obtain 177 Lu of desired purity amenable for the preparation of radiopharmaceuticals [62].…”

Production of the positron emitter 51Mn via the 50Cr(d, n) reaction: targetry and separation of no-carrier-added radiomanganese

“…In cases of two additionally placed 30 µm Al • foils in front to prevent potential losses of target material during the irradiation, the deuteron energy incident on the matrix pellet was 12.8 MeV. The target system is similar to the one used by Denzler et al [11]. Irradiation tests showed that for focussed beams the upper flux limit was already reached at 2 µA.…”

“…Production tests were conducted with a 2π water-cooled target holder of copper [11] and 20 mg (0.4 mmol) of 95% enriched 50 Cr in the form of Al 4 ·CrCl 3 pellets. The resulting experimental yields, normalized to 1 µA h, are listed in Table 2.…”

“…As a further step, quantitative in vivo data in man can be obtained via the non-invasive techniques Single Photon Emission Computed Tomography (SPECT) and Positron Emission Tomography (PET). While in the case of Gd-compounds the SPECT nuclide 147 Gd (t 1/2 = 38.1 h, E γ = 229 keV (61%)) has been shown to be suitable [11], manganese offers two PET nuclides, namely 52m Mn (t 1/2 = 21.1 min, I β + = 97%, E β + (max) = 0.6 MeV, IT = 1.75%) and 51 Mn (t 1/2 = 46.2 min, I β + = 97%, E β + (max) = 2.5 MeV). 52m Mn of high radionuclidic purity is only available from the 52 Fe/ 52m Mn generator [12][13][14][15][16][17][18][19][20], since direct nuclear reactions, such as the 52 Cr( p, 2n) process, always lead to an isomeric mixture [3,4].…”

Separation of No-Carrier Added 147,149Gd and 147Eu Produced in 70 MeV 11B Irradiated Praseodymium Foil Target

“…enriched "'Sm203 and '•^SmjOj respectively The Separation of carrier-free gadolinium and europium from the bulk target matrix of samarium oxide was performed by cementation with Na-amalgam followed by ion-exchange chromatography using a-hydroxyisobutyric acid as an eluting agent [7]. Carrier-free mixture of produced in a neutron activated natural samarium target was separated by eluting with a-HIBA from a Dowex 50 column [8].…”