Fatemeh Mohammadpour-Ghazi - Radiation Application Research School, Nuclear Science and Technology Research Institute, Tehran, Iran
Hassan Yousefnia - Radiation Application Research School, Nuclear Science and Technology Research Institute, Tehran, Iran
Samaneh Zolghadri - Radiation Application Research School, Nuclear Science and Technology Research Institute, Tehran, Iran
Mohammad Yarmohammadi - Radiation Application Research School, Nuclear Science and Technology Research Institute, Tehran, Iran
Behrouz Alirezapour - Radiation Application Research School, Nuclear Science and Technology Research Institute, Tehran, Iran
Ali Rahiminejad - Radiation Application Research School, Nuclear Science and Technology Research Institute, Tehran, Iran
Gholamreza Aslani - Radiation Application Research School, Nuclear Science and Technology Research Institute, Tehran, Iran

Introduction: Particular characteristics of ۸۹Zr to produce various labeled compounds are crucial for developing radioimmunopharmaceuticals for clinical trials. This study aimed to produce ۸۹Zr for radiolabeling purposes as radioimmunoPET grade precursor.  Methods: The computational calculations for ۸۹Zr production via ۸۹Y(p,n)۸۹Zr reaction were performed using TALYS-۱.۸ and ALICE-۹۱. ۸۹Zr was produced by the proton bombardment of the yttrium pellet using a ۳۰ MeV cyclotron. ZR resin was used for the separation of ۸۹Zr from the target. The radionuclidic purity was assessed by a high purity germanium detector. The inductively coupled plasma spectrometry and instant thin layer chromatography methods were considered for chemical and radiochemical purity assessments, respectively. The biodistribution of [۸۹Zr]Zr-oxalate was studied in Wistar rats by both sacrification and imaging. [۸۹Zr]Zr-DFO-trastuzumab was produced as a proof of concept for a radioimmunoPET labeling.Results: Considering the cross-section of ۸۹Y(p,n)۸۹Zr reaction, ۱۴ MeV proton energy was selected for ۸۹Zr production, while the yttrium pellet target was irradiated at least for ۱۲۵ µAh,. ۸۹Zr was finally prepared with a yield of ۲۵.۹±۱.۴۸ MBq/µAh, a specific activity of ۳۴۴.۱ MBq/µg, the radionuclidic and radiochemical purity higher than ۹۹.۹۹% and ۹۹%, respectively. Total amount of the metal ions in the final solution was less than ۰.۱ ppm. Biodistribution of [۸۹Zr]Zr-oxalate demonstrated high accumulation in the bone, lungs, and heart. [۸۹Zr]Zr-DFO-trastuzumab was produced with a radiochemical purity higher than ۹۹% and specific activity of ۷۴ GBq/g in about ۲ hours.Conclusion: [۸۹Zr]Zr-oxalate was produced with suitable activity and high purity for the preparation of the radioimmunopharmaceuticals.

Zirconium-۸۹, Production, Radiolabeled compounds, cyclotron