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Wyświetlanie 1-3 z 3
Tytuł:
Production and quality control of 65Zn radionuclide
Autorzy:
Rowshanfarzad, P.
Jalilian, A.
Sabet, M.
Powiązania:
https://bibliotekanauki.pl/articles/148866.pdf
Data publikacji:
2005
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
zinc-65
production
cyclotron
radiochemical separation
quality control
Opis:
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.
Źródło:
Nukleonika; 2005, 50, 3; 97-103
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Production and quality control of 66Ga radionuclide
Autorzy:
Sabet, M.
Rowshanfarzad, P.
Jalilian, A.
Ensaf, M.
Rajamand, A.
Powiązania:
https://bibliotekanauki.pl/articles/146278.pdf
Data publikacji:
2006
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
gallium-66
cyclotron
radiochemical separation
target recovery
Opis:
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.
Źródło:
Nukleonika; 2006, 51, 3; 147-154
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Production, quality control and initial imaging studies of [82mRb]RbCl for PET studies
Autorzy:
Rowshanfarzad, P.
Jalilian, A.
Kiyomarsi, M.
Sabet, M.
Karimian, A.
Moradkhani, S.
Mirzaii, M.
Powiązania:
https://bibliotekanauki.pl/articles/146165.pdf
Data publikacji:
2006
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
rubidium-82m
quality control
animal study
cyclotron
Opis:
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.
Źródło:
Nukleonika; 2006, 51, 4; 209-215
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
    Wyświetlanie 1-3 z 3

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