(450d) Automated Systems for Processing of Cyclotron Irradiated Solid Targets | AIChE

(450d) Automated Systems for Processing of Cyclotron Irradiated Solid Targets

Authors 

Lapi, S. E. - Presenter, Washington University
Madrid, E. - Presenter, Washington University
Voller, T. - Presenter, Washington University
Carey, P. - Presenter, Washington University
Kume, M. - Presenter, Washington University
Sultan, D. - Presenter, Washington University
Welch, M. - Presenter, Washington University


Development of agents for Positron Emission Tomography (PET) is a rapidly growing field.  The isotopes 18F and 11C are the most commonly used for labeling compounds of interest, but the short half-lives of these isotopes (120 minutes and 20 minutes respectively) often limits the studies which can be conducted to ones which occur on a rapid timescale.  The production of longer-lived positron-emitting radionuclides (t1/2= hours-days) often requires the use of solid materials as targets.         The processing of these solid targets presents different challenges than the liquid targets (used for production of 18F and 13N) or gas targets (used for the production of 11C).  We have developed automated systems for the production of 64Cu via the 64Ni(p,n) reaction, 76,77Br via the 76,77Se(p,n) reaction and for 86Y via the 86Sr(p,n) reaction.  These systems are at different stages of development, with the 64Cu processing system being the most advanced.

64Cu (t1/2= 12.7 hours) is an important radioisotope as it decays via both positron emission and negatron emission. Thus it has sparked interest as a potential isotope for both imaging and therapy.  We have been producing this isotope for over 15 years and are currently shipping out substantial quantities (200-400 mCi) to some 12-15 institutions on a weekly basis for both preclinical studies and clinical trials.  This isotope is produced via irradiation of an enriched 64Ni target plated on a gold disk support.  After irradiation, the target material is dissolved and the 64Cu/64Ni separation is conducted remotely via ion exchange.  The system is designed in such a manner as to recover the 64Ni target material for recycling.

76,77Br are two isotopes which are of interest as an imaging therapy pair.   Our group has been producing these radiobromine isotopes for imaging and therapy using brominated estrogen and androgen analogues.  The target material is doubly enriched 63Cu276,77Se.  The purpose of the enriched 63Cu is to prevent the long-lived contaminant 65Zn (t1/2 = 244 d) from building up in the system.  The radiobromine is extracted via a remote distillation apparatus where the target is heated in a quartz tube furnace to distill the radiobromine which subsequently condenses on a cooler section of the tube.  The radioactivity is eluted from the tube and the target can be re-irradiated.

86Y is of interest as an imaging analogue for 90Y therapeutics.  This is desirable as 90Y is a pure β emitter and thus understanding the biodistribution and pharmacokinetics of new agents labeled with this isotope is difficult.  These compounds can be labeled with 86Y and imaging studies can be carried out before the therapeutic experiments with 90Y.  86Y is produced via proton bombardment of 86Sr in the form of 86SrO.  The target material is dissolved and separated using the differences in solubility of strontium and yttrium in acidic and basic solutions.  This technique is currently in the process of being automated.

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