ABSTRACT
A conceptual flowsheet has been developed for the separation of (177)Lu from a 300 mg neutron irradiated (176)Yb enriched target. The key component of the process is an extraction chromatographic (EXC) resin containing 2-ethylhexyl 2-ethylhexylphosphonic acid (HEH[EHP]) sorbed onto a 25-53 microm Amberchrom CG-71 substrate. The process is divided into three sections: (1) front-end target removal system, (2) primary separation system and (3) secondary separation system. Each section involves the separation of Yb and Lu using the HEH[EHP] resin followed by concentration and acid adjustment of the Lu-rich eluate using an EXC material containing a diglycolamide extractant. The use of the diglycolamide EXC material is a significant feature of the flowsheet, allowing one to avoid lengthy evaporations and acidity adjustments between successive HEH[EHP] column runs while removing adventitious impurities from the (177)Lu. The overall recovery of (177)Lu is estimated at 73% with an overall decontamination factor from Yb of 10(6). The overall processing time can be as short as 4h.
