Персона: Терехова, Анна Михайловна
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ИАТЭ НИЯУ МИФИ
ИАТЭ НИЯУ МИФИ был образован в 1953 г. как вечернее отделение МИФИ. В 2009 г. ИАТЭ официально получил статус обособленного структурного подразделения НИЯУ «МИФИ», что дало новый мощный импульс для развития образовательной и научной деятельности на основе инновационной составляющей. В соответствии с лицензией Минобрнауки России ИАТЭ ведет образовательную деятельность в рамках очной, очно-заочной и заочной форм обучения. В настоящее время в ИАТЭ НИЯУ МИФИ осуществляется подготовка по очной форме обучения: бакалавриат- 16 направлений, специалитет – 4 направления, магистратура- 12 направлений; по очно-заочной: бакалавриат- 4 направления, специалитет – 1 направление; по заочной: бакалавриат- 3 направления, специалитет- 2 направления; аспирантура – 18 направлений.
В структуре ИАТЭ 9 факультетов: физико-энергетический, естественных наук, кибернетики, социально-экономический, медицинский, вечерний, заочного обучения, подготовительный, повышения квалификации и профессиональной переподготовки специалистов. Образовательный процесс обеспечивают 18 общеобразовательных и 22 выпускающие кафедры.
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Анна Михайловна
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- ПубликацияОткрытый доступInvestigation the possibility of burning Cm a curium fuel reactor(2020) Dikova, T. S.; Karazhelevskaya, Yu. E.; Terekhova, A. M.; Терехова, Анна Михайловна© Published under licence by IOP Publishing Ltd.Radioactive waste management is one of the main tasks of the nuclear power industry. Spent nuclear fuel poses a threat to the environment if it leaks from the storage facility. A possible solution to reduce waste storage and reduce the economic pressure of natural uranium shortages is to use minor actinides as fuel for nuclear reactors. This article is dedicated to the possibility of burning Cm in a reactor with curium fuel, as a result of which It can be used as fuel for a nuclear reactor. The purpose of the research is to study the possibility of creating a model of a reactor with curium fuel. Calculations were performed for a simplified single-zone model of the RBEC reactor using the Serpent software package. Calculations have shown that the use of the actinides as an alternative fuel is possible. That can later play an important role in reducing emissions of nuclear waste in nuclear power.
- ПубликацияОткрытый доступIrregularity of plutonium isotopic composition of the BREST-OD-300 initial load(2020) Zlobin, A. S.; Karazhelevskaya, Y. E.; Levon, M. A.; Terekhova, A. M.; Терехова, Анна Михайловна© Published under licence by IOP Publishing Ltd.This article is dedicated observation of irregularity of plutonium isotopic composition of the BREST-OD-300 initial load. The purpose of the research is to study the effect of the plutonium isotopic composition in the nitride fuel of the BREST-OD-300 reactor core starting load on the reactivity reserve. The calculations is creating by writing simplified three-dimensional geometry of the BREST-OD-300 reactor in software package "SERPENT". There are five options in the fuel assemblies locations are considered with different cases of using the plutonium isotopic composition with deviations for some isotopes. Calculations have shown that the deviation of the plutonium isotope composition from the design values of the fuel loading of the BREST-OD-300 reactor does not affect the stability of reactivity during fuel burnout within the effective fraction of delayed neutrons. In the course of the research, changes in the effective multiplication coefficient are obtained over five years of reactor operation. The value of this indicator does not depend much on the plutonium deviation in the considered variations in the arrangement of fuel assemblies in the reactor core.
- ПубликацияОткрытый доступInvestigation of the small break conditions in the primary circuit of a VVER-1000 reactor(2019) Belozerov, V. I.; Terehova, A. M.; Терехова, Анна Михайловна
- ПубликацияОткрытый доступInfluence of boron enrichment in control rods on neutron-physical characteristics of the core of the reactor VVER(2019) Terekhova, A. M.; Levchenko, Y. V.; Matveeva, T. V.; Borisov, I. S.; Терехова, Анна Михайловна© Published under licence by IOP Publishing Ltd. Boron is widely used in nuclear power as a neutron absorber material, thereby creating the possibility of controlling a nuclear reactor by changing the neutron multiplication factor. Natural boron contains about 20% 10 B and 80% 11 B with absorption sections respectively 3840 barn and 0.05 barn. The paper deals with changes in neutron-physical parameters of the reactor core of VVER type when the isotope content of 10 B in boron carbide of absorber rods (AR) of the control and protection system (CPS) and in boric acid solution in the coolant of the VVER reactor is varied, and also analyzes the practicality of increasing the enrichment of 10 B isotope in the control rods (CR). The model of VVER-1200 fuel assembly (FA) was used for calculations. In the course of work were modelled and the calculations of the three models of the coolant with different boric acid concentrations, as well as two models of AS with different enrichment in the isotope 10 B.