Počet záznamů: 1  

Activation cross-section measurement of fast neutron-induced reactions in Al, Au, Bi, Co, F, Na, and Y

  1. 1.
    0553629 - ÚJF 2023 RIV NL eng J - Článek v odborném periodiku
    Jarošík, J. - Wagner, Vladimír - Majerle, Mitja - Chudoba, Petr - Burianová, N. - Štefánik, Milan
    Activation cross-section measurement of fast neutron-induced reactions in Al, Au, Bi, Co, F, Na, and Y.
    Nuclear Instruments & Methods in Physics Research Section B. Roč. 511, JAN (2022), s. 64-74. ISSN 0168-583X. E-ISSN 1872-9584
    Grant CEP: GA MŠMT EF16_013/0001812
    Výzkumná infrastruktura: e-INFRA CZ - 90140; CANAM II - 90056
    Institucionální podpora: RVO:61389005
    Klíčová slova: Quasi-monoenergetic neutron source * Cross section * Pure positron emitter * Cascade decay
    Obor OECD: Nuclear related engineering
    Impakt faktor: 1.3, rok: 2022
    Způsob publikování: Omezený přístup
    https://doi.org/10.1016/j.nimb.2021.10.018

    This paper describes cross-section measurements by means of the neutron activation method using an accelerator-driven fast neutron source at the Nuclear Physics Institute of the Czech Academy of Sciences in Rel. It extends previous studies published in papers (Vrzalova et al. (2013), Chudoba et al. (2018)). A quasimonoenergetic neutron source based on the p+Li(C) reaction was used to irradiate Al, Au, Bi, Co, NaF, and Y samples with neutrons at the energies of 17.5(10) MeV, 19.8(9) MeV and 27.5(7) MeV. Irradiated foils were analyzed by means of gamma-ray spectrometry and reaction yields were obtained. Cross sections of several fast neutron-induced reactions were determined on the basis of the measurement of neutron spectra and their corresponding reaction yields. The production cross sections of isomeric states were determined as well. This paper also describes the measurements of the positron emitters using annihilation gamma-ray spectrometry. The sources of uncertainties in the various parts of the experiment are discussed. The resulting cross sections might be useful for the further development of advanced nuclear reactors and fast neutron dosimetry.
    Trvalý link: http://hdl.handle.net/11104/0328379

     
     
Počet záznamů: 1  

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