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    Wyświetlanie 1-7 z 7
    Tytuł:
    Cyclotron production of 68Ga via proton-induced reaction on 68Zn target
    Autorzy:
    Sadeghi, M.
    Kakavand, T.
    Rajabifar, S.
    Mokhtari, L.
    Rahimi-Nezhad, A.
    Powiązania:
    https://bibliotekanauki.pl/articles/146448.pdf
    Data publikacji:
    2009
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    production
    gallium-68
    zinc-68
    PET
    cyclotron
    Opis:
    68Ga is an important positron-emitting radionuclide for positron emission tomography. In this work 68Ga was produced via the 68Zn(p,n)68Ga nuclear reaction. 68Zn electrodeposition on a copper substrate was carried out by alkaline cyanide baths. 68Zn target was irradiated with a 15 MeV proton beam and a 150 mi A current. The production yield achieved was 136 mCi/ mi Aźh (5.032 GBq/mi Aźh). 68Ga was separated from zinc and copper by a combination of cation exchange chromatography and liquid-liquid extraction methods.
    Źródło:
    Nukleonika; 2009, 54, 1; 25-28
    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:
    Preparation and evaluation of a [66Ga]gallium chitosan complex in fibrosarcoma bearing animal models
    Autorzy:
    Pourjavadi, A.
    Akhlaghi, M.
    Jalilian, A. R.
    Powiązania:
    https://bibliotekanauki.pl/articles/147067.pdf
    Data publikacji:
    2011
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    chitosan
    gallium-66
    internal radiotherapy
    fibrosarcoma
    intratumoral injection
    Opis:
    [66Ga]gallium chitosan complex was prepared with a high radiochemical purity (greater than 99%) in dilute acetic acid solution. The radiochemical purity of [66Ga]gallium chitosan complex was checked by using paper chromatography technique. The prepared complex solution was injected intratumoral to fibrosarcoma-bearing mice and the leakage of radioactivity from injection site was investigated. Approximately, 85.4% of the injected dose was retained in the injection site 54 h after injection and most of the leaked radioactivity was accumulated in the blood, liver (0.5%) and lung (6.5%).
    Źródło:
    Nukleonika; 2011, 56, 1; 35-40
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Uranium and neodymium partitioning in alkali chloride melts using low-melting gallium-based alloys
    Autorzy:
    Melchakov, S. Y.
    Maltsev, D. S.
    Volkovich, V. A.
    Yamshchikov, L. F.
    Lisienko, D. G.
    Osipenko, A. G.
    Rusakov, M. A.
    Powiązania:
    https://bibliotekanauki.pl/articles/146407.pdf
    Data publikacji:
    2015
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    neodymium
    uranium
    gallium
    separation factor
    reductive extraction
    pyrochemical reprocessing
    Opis:
    Partitioning of uranium and neodymium was studied in a ‘molten chloride salt – liquid Ga-X (X = In or Sn) alloy’ system. Chloride melts were based on the low-melting ternary LiCl-KCl-CsCl eutectic. Nd/U separation factors were calculated from the thermodynamic data as well as determined experimentally. Separation of uranium and neodymium was studied using reductive extraction with neodymium acting as a reducing agent. Efficient partitioning of lanthanides (Nd) and actinides (U), simulating fission products and fissile materials in irradiated nuclear fuels, was achieved in a single stage process. The experimentally observed Nd/U separation factor valued up to 106, depending on the conditions.
    Źródło:
    Nukleonika; 2015, 60, No. 4, part 2; 915-920
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Development of [66Ga]oxine complex; a possible PET tracer
    Autorzy:
    Jalilian, A.
    Rowshanfarzad, P.
    Sabet, M.
    Rahiminejad-Kisomi, A.
    Rajamand, A.
    Powiązania:
    https://bibliotekanauki.pl/articles/146276.pdf
    Data publikacji:
    2006
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    gallium-66
    oxine
    positron emission tomography
    blood cell labeling
    stability
    Opis:
    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.
    Źródło:
    Nukleonika; 2006, 51, 3; 155-159
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Preparation and primary evaluation of 66Ga-DTPA-chitosan in fibrosarcoma bearing mice
    Autorzy:
    Akhlaghi, M.
    Pourjavadi, A.
    Powiązania:
    https://bibliotekanauki.pl/articles/147065.pdf
    Data publikacji:
    2011
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    DTPA-chitosan
    degree of modification (DM)
    gallium-66
    radiolabeled
    intratumoral injection
    Opis:
    Chitosan was chemically modified by diethylenetetraaminepentaacetic acid (DTPA) in different degrees of modification (DM = 6.1, 10.3, 15.7 and 20.9%). DTPA-chitosans were radiolabeled with gallium-66 radionuclide. The effect of several factors on labeling yield such as degree of modification, acidity and concentration of DTPA-chitosan solution, contact time and radioactivity was investigated. Radiolabeled DTPA chitosans were intratumorally injected to fibrosarcoma bearing mice and the leakage of radioactivity from the injection site was evaluated. In comparison with chitosan, all DTPA chitosans showed better efficiency in preventing the leakage of radioactivity from tumor lesion and DTPA-chitosan (DM = 10.3%) was the best which led to remaining 97% of injected dose in the injection site after 54 h of injection. The highest leaked radioactivity from the injection site was in the lungs, liver, spleen and the kidneys. Our results indicated that the DTPA modified chitosan can be an effective carrier for therapeutic radionuclides for tumor treatment by the intratumoral injection technique.
    Źródło:
    Nukleonika; 2011, 56, 1; 41-47
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Damage distributions in GaAs single crystal irradiated with 84Kr (394 MeV), 209Bi (710 MeV) and 238U (1300 MeV) swift ions
    Autorzy:
    Didyk, A. Y.
    Komarov, F. F.
    Vlasukova, L. A.
    Gracheva, E. A.
    Hofman, A.
    Yuvchenko, V. N.
    Wiśniewski, R.
    Wilczyńska, T.
    Powiązania:
    https://bibliotekanauki.pl/articles/146738.pdf
    Data publikacji:
    2008
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    semiconductors
    gallium arsenide
    swift heavy ions
    inelastic energy loss
    atomic force microscopy (AFM)
    Opis:
    We are presenting a study of damage distribution in GaAs irradiated with 84Kr ions of energy EKr = 394 MeV up to the fluence of 5 × 1012 ion/cm-2. The distribution of damage along the projected range of 84Kr ions in GaAs was investigated using selective chemical etching of a single crystal cleaved perpendicularly to the irradiated surface. The damage zone located under the Bragg peak of 84Kr ions was observed. Explanation of the observed effects based on possible processes of channeling of knocked target atoms (Ga and As) is proposed.
    Źródło:
    Nukleonika; 2008, 53, 2; 77-82
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
      Wyświetlanie 1-7 z 7

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