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Targetry and radiochemistry for no-carrier-added production of 117,118m,119,120m,122Sb

Sadeghi M., Aboudzadeh Rovais M. R., Enferadi M., Sarabadani P.

Nukleonika

2011

Vol. 56, No. 1

9-15

Targetry of natSn-target on Cu substrate was investigated for the production of 117,118m,119,120m,122Sb. The electrodeposition experiments were carried out using potassium stannate trihydrate and potassium hydroxide. The optimum conditions of the electrodeposition of tin were as follows: 40 g/L natSn, temperature 75°C and current density (dc) used throughout of 50 mA/cm2. The deposited target was irradiated at 160 ěA current and 16 MeV proton beam (10 min). Separation of no-carrier-added (nca) 117,118m,119,120m,122Sb from the irradiated natSn target hydrochloric solution was investigated using silica-gel column chromatography.

Routine simultaneous production of no-carrier-added high purity 64Cu and 67Ga

Al Rayyes A. H., Ailouti Y.

Nukleonika

2011

Vol. 56, No. 4

259-262

A routine production method of no-carrier-added 64Cu was performed. A copper target support is electroplated by gold then an optimized thickness of enriched 68Zn layer is deposited. The 68Zn target was bombarded with a 23.5 MeV and 250 miA proton beam, generating the main nuclear reactions 68Zn(p,2n)67Ga and 68Zn(p,alfa n)64Cu. A semi-automated separation method using a chromatographic column system was developed for 64CuCl2 production. A 600 mCi batch of 64Cu is produced at the end of separation and purification chemistry. The radionuclidic purity of 64Cu was less than 98% as required by the United States and European Pharmacopoeias. Radiochemical purity and activity concentration is suitable for labeling different ligands to produce diagnostic and therapeutic radiopharmaceuticals.

Design and manufacture of krypton gas target for 81Rb production at a 30 MeV cyclotron

Rovais M.R.A., Mirzaii M., Kiyomarsi M., Yousefi K., Shadanpour N., Ensaf M. R.

Nukleonika

2010

Vol. 55, No. 2

225-231

The cyclotron of nuclear medicine research group at the Agricultural, Medical and Industrial Research School (AMIRS) has been producing several radionuclides such as 201Tl, 67Ga, 18F and 81Rb for nuclear medicine centers. Gas targets are utilized in a variety of cyclotron producing radionuclides which are used in nuclear medicine centers. We report a method for the design and manufacture of a cyclotron gas target which facilitates both the collection and processing of the krypton gas target as well as the desired 81Rb. In this study a gas target was designed for routine production of 81Rb (for a 81Rb/81mKr generator) through the nuclear reaction natKr(p,2n)81Rb → 81mKr. The incident energy of protons on the target was 26.5 MeV. The gas target was made of stainless steel. The length of the target was 251 mm with double titanium windows, 20 μm in thickness. A production yield of 3.18±0.27 mCi/μA·h was obtained which was more than 80% of the calculated yield (4.1 mCi/μA·h).