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Савандер, Владимир Игоревич

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Институт ядерной физики и технологий
Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.
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Владимир Игоревич
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2019 - 20202
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Автор: Demin, V. M. ×

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    The effect of burnable absorbers (Gd and Eu) on the neutronphysical characteristics of fuel assemblies of VVER-1000 reactors
    (2019) Abu, Sondos, M. A.; Demin, V. M.; Savander, V. I.; Демин, Виктор Максимович; Савандер, Владимир Игоревич
    © 2019 Published under licence by IOP Publishing Ltd. The problem of the use of burnable absorbers (BAs) in VVER-type reactors is considered to reduce the volume of "liquid" regulation of excess reactivity margin for fuel burnup. As such, natural gadolinium and europium are considered in the form of Gd 2 O 3 and Eu 2 O 3 , placed in integrated form with uranium fuel in fuel rods. The ratio of fuel rods with BAs and conventional fuel elements is 1:6. Variants of both the homogeneous location of the BAs and heterogeneous, including for the mixed use of these BAs were considered. The strong influence of the BAs composition and their location in the fuel elements on the dependence of the multiplication factor on fuel burnup is shown.
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    Estimation of the Duration of Cooling Time of the SFA of the VVER-1200 Reactor Depending on the Type of Transport Container
    (2020) Demin, V. M.; Savander, V. I.; Ternovykh, M. Y.; Abu, Sondos, M. A.; Демин, Виктор Максимович; Савандер, Владимир Игоревич; Терновых, Михаил Юрьевич
    © 2020, Pleiades Publishing, Ltd.Abstract: As the burnup increases, the requirements of nuclear and radiation safety for spent nuclear fuel (SNF) at the subsequent stages of operation grow. The analysis and estimation of the required cooling time of the spent fuel assemblies (SFAs) of the VVER-1200 reactor for transportation in various types of transport containers (TUK-13 and TUK-141O) are performed. The estimates are based on the analysis of residual energy release and gamma-radiation intensity of SNF depending on the cooling time for different burnups. The data on the absorbed dose rate of neutron and gamma radiation from SNF after 4 and 5 yr of cooling are presented.