Wyniki wyszukiwania - BazTech

1

Thick zinc electrodeposition on copper substrate for cyclotron production of 64Cu

Sadeghi M., Amiri M., Rowshanfarzad P., Gholamzadeh Z., Ensaf M.

Nukleonika

|

2008

|

Vol. 53, No. 4

155-160

EN

Zinc-68 electrodeposition on a copper substrate was investigated for the production of 64Cu radionuclide. The electrodeposition experiments were carried out by acid plating baths. Operating parameters such as pH, temperature, and current density are also optimized. The current efficiency was measured at different current densities. The optimum conditions of the zinc electrodeposition were as follows: 6.2 gźl-1 zinc, pH = 3, dc current density of ca. 85.54 mAźcm-2 at 30°C with 98% current efficiency. SEM photomicrographs demonstrated fine-grained structure of the deposit obtained from the optimum bath.

2

Production, quality control and initial imaging studies of [82mRb]RbCl for PET studies

Rowshanfarzad P., Jalilian A., Kiyomarsi M., Sabet M., Karimian A., Moradkhani S., Mirzaii M.

Nukleonika

|

2006

|

Vol. 51, nr 4

209-215

EN

Rubidium-82m was prepared via 15.4 MeV proton irradiation of a krypton-82 gaseous target (30% enrichment). Washing the target chamber with hot water yielded a Rb-82m containing solution, which was further purified using short column chromatography in order to remove organic/inorganic impurities. The flowthrough was formulated in normal saline for injection. Radionuclide, radiochemical and chemical purity tests were performed prior to administration to rats for imaging (radiochemical yield: 95-97%, radiochemical purity > 97%). Preliminary dual-head coincidence studies were performed to determine the distribution of [82mRb]Rb in normal rats. For biodistribution studies, Rb-81 was injected to rats and tracer accumulation in heart, GI and bladder was determined after sacrification in time intervals. A yield of 1.3 GBq at EOB, 235.7 MBq/mAh was obtained.

3

Production and quality control of 66Ga radionuclide

Sabet M., Rowshanfarzad P., Jalilian A., Ensaf M., Rajamand A.

Nukleonika

|

2006

|

Vol. 51, nr 3

147-154

EN

The purpose of this study was to develop the required targetry and radiochemical methods for production of 66Ga, according to its increasing applications in various fields of science. The 66Zn(p,n)66Ga reaction was selected as the best choice for the production of 66Ga. The targets were bombarded with 15 MeV protons from cyclotron (IBA-Cyclone 30) at the Nuclear Research Center for Agriculture and Medicine (NRCAM) with a current of 180 mA for 67 min. ALICE and SRIM (Stopping and Range of Ions in Matter) nuclear codes were used to predict the optimum energy and target thickness. Targets were prepared by electroplating 95.73% enriched 66Zn on a copper backing. Chemical processing was performed by a no-carrier-added method consisting of ion exchange chromatography and liquid-liquid extraction. Anion exchange chromatography was also used for the recovery of target material. Quality control of the product was carried out in two steps of chemical and radionuclide purity control. The activity of 66Ga was 82.12 GBq at EOB and the production yield was 410.6 MBq/mAh. The radiochemical separation yield was 93% and the yield of chemical recovery of the target material was 97%. Quality control tests showed a radionuclide purity higher than 97% and the amounts of chemical impurities were in accordance with the United States Pharmacopoeiae levels.

4

Preparation of [61Cu]DTPA complex as a possible PET tracer

Jalilian A., Rowshanfarzad P., Sabet M., Kamalidehghan M.

Nukleonika

|

2006

|

Vol. 51, nr 2

111-117

EN

Copper-61 (T1/2 = 3.33 h) produced via the 64Zn(p,alfa)61Cu nuclear reaction, using a natural zinc target, was separated from the irradiated target material by two ion exchange chromatography steps and was used for the preparation of [61Cu]-diethylenetriaminepentacetate ([61Cu]DTPA) using freshly-prepared DTPA cyclic dianhydride. An electroplated natural zinc layer on a gold-coated copper backing was irradiated with 22 MeV protons (22 12 MeV on the target, 180 miA irradiation, 3.2 h, final activity 220 GBq of 61Cu2+, RCY > 95%, radionuclidic purity > 99%, 60Cu as the only radionuclidic impurity; T1/2 = 23.7 min). Colorimetric methods showed that traces of chemical impurities in the product were below the accepted limits. The solution of [61Cu]DTPA was prepared with a radiochemical yield of more than 80% starting with 61CuOAc ligand at room temperature after 30 min. RTLC showed the radiochemical purity of more than 99%. The specific activity obtained was about 9.1 TBq/mmol. The tracer was shown to be stable in the final product and in the presence of human serum at 37°C up to 3 h.

5

Development of [66Ga]oxine complex; a possible PET tracer

Jalilian A., Rowshanfarzad P., Sabet M., Rahiminejad-Kisomi A., Rajamand A.

Nukleonika

|

2006

|

Vol. 51, nr 3

155-159

EN

The aim of this work is development of a possible blood cell labeling agent for ultimate use in PET. Gallium-66 (T1/2 = 9.49 h) is an interesting radionuclide that has a potential for positron emission tomography (PET) imaging of biological processes with intermediate to slow target tissue uptake. Oxine has been labeled with this radionuclide in the form of [66Ga]gallium chloride for its possible diagnostic properties. In this study, 66Ga was produced at a 30 MeV cyclotron (IBA-Cyclone 30) via the 66Zn(p,n)66Ga reaction. The production yield was 445.5 MBq/mAh. The [66Ga]oxine complex was obtained at pH = 5 in phosphate buffer medium at 37°C in 10 min. Radio-TLC showed a radiochemical purity of more than 98 š 2%. The chemical stability of the complex was checked in vitro with a specific activity of 1113 GBq/mmol. The serum stability and log P of the complex were calculated. The produced [66Ga]oxine can be used for diagnostic studies, due to its desirable physico-chemical properties both in vitro and in vivo according to internationally accepted limits.

6

Production and quality control of 65Zn radionuclide

Rowshanfarzad P., Jalilian A., Sabet M.

Nukleonika

|

2005

|

Vol. 50, nr 3

97-103

EN

Zinc-65 was produced in the Nuclear Research Center for Agriculture and Medicine (NRCAM) by the bombardment of natural copper targets with 30 MeV protons via the 65Cu(p,n)65Zn nuclear reaction. Natural copper was used instead of enriched 65Cu because of the quick decay of undesired radioisotopes. It was also more desirable for cost effectiveness. Cross-section calculations were performed by ALICE nuclear code and the results were compared with the experimental data given in the literature, which showed good agreement. A 160 mi m copper layer target was bombarded with a 150 miA current of 30 MeV protons for 20 min, which resulted in 170 MBq activity of 65Zn product. The yield was 3.4 MBq/miAh. The concentration of the product was 6.8 MBq/ml. Radiochemical separation was carried out by anion exchange chromatography with the yield of about 98%. Quality control of the final product showed a radionuclide purity of more than 98% and no traces of possible impurities (copper) were detected by a colorimetric method with a 1 ppm detection limit using dithizone as the reagent. The materials used for targetry and chemical separation were quite cost-effective.

7

Development of 111In-DTPA-human polyclonal antibody complex for long-term inflammation/infection detection

Jalilian A., Rowshanfarzad P., Shafaii K., Kamali-Dehghan M., Moafian J., Akhlaghi M., Babaii M., Rajabifar S., Mirzaii M.

Nukleonika

|

2005

|

Vol. 50, nr 3

91-96

EN

Human polyclonal antibody (HIgG) was successively labeled with 111In-indium chloride after residulation with freshly prepared cyclic DTPA-dianhydride. The best results of the conjugation were obtained by the addition of solid DTPA-dianhydride (0.1 0.3 mg) to 100 mi l of the HIgG solution (0.2 0.4 mg/ml) at pH = 6 in phosphate buffer media at 25°C with continuous stirring for 30 min. Radio-thin-layer chromatography showed an overall radiochemical yield of 96 99% at optimized conditions (specific activity = 300 500 MBq/mg, radiochemical purity >98%). The final isotonic 111In-DTPA-HIgG complex was checked by radio-TLC to ensure the formation of only one species followed by filtration through a 0.22 mi filter. Preliminary long-term in vivo studies in turpentine-oil induced inflammation in rat model was performed to determine late complex distribution of the radioimmunoconjugate. The target/skin and target/ blood ratios were 27 and 51 after 24 h, and 23 and 51 after 110 h, showing a high selectivity of the radiopharmaceutical for inflammatory lesions.