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Distribution of neutrons and protons in elongated targets

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    0542157 - ÚJF 2022 RIV FR eng C - Konferenční příspěvek (zahraniční konf.)
    Zeman, M. - Adam, J. - Baldin, A. A. - Brunciakova, M. - Gustov, S. A. - Katovsky, K. - Khushvaktov, J. - Král, D. - Solnyshkin, A. A. - Svoboda, J. - Šťastný, O. - Tichý, Pavel - Tyutyunikov, S. - Vrzalová, Jitka - Wagner, Vladimír - Závorka, L.
    Distribution of neutrons and protons in elongated targets.
    EPJ Web of Conferences. Vol. 239. Les Ulis: E D P Sciences, 2020, č. článku 06005. ISBN 978-2-7598-9106-1. ISSN 2100-014X.
    [International Conference on Nuclear Data for Science and Technology (ND2019). Beijing (CN), 19.05.2019-24.05.2019]
    Grant CEP: GA MŠk LTT18021
    Institucionální podpora: RVO:61389005
    Klíčová slova: neutron distribution * elongated targets * neutron field
    Obor OECD: Nuclear physics

    Analysis of neutron distribution was carried out for two elongated targets. The targets have cylindrical shape and are made of lead and carbon, respectively. The dimensions are approximately one meter in length and 19 cm in diameter. The targets were irradiated with 660 MeV proton beam at Phasotron accelerator at the Joint Institute for Nuclear Research. The total number of protons was 2.35(18)E15 for the experiment with carbon target and the total number of particles at the second experiment was 2.32(19)E15. The produced neutron field was monitored by cobalt threshold activation detectors at various positions. The activation detectors were measured by means of gamma spectroscopy using HPGe detectors. Reaction rates of different radionuclides produced in the activation detectors were determined and the results from both experiments were compared. The ratios were calculated for 7 reactions produced in cobalt detectors. The ratio of the reaction rates shows that the number of residual nuclei with higher threshold energies is higher for experiment with carbon target than for the experiment with the lead target.
    Trvalý link: http://hdl.handle.net/11104/0319632

     
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