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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- 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.
- ПубликацияТолько метаданныеInvestigation of the possibility of AM-241 incineration and transmutation in ameritium-fueled reactor(2019) Korobeinikov, V. V.; Karazhelevskaya, Yu. E.; Kolesov, V. V.; Terekhova, A. M.; Терехова, Анна Михайловна© 2019 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.Studies were carried out on the transmutation of americium in nuclear reactor loaded with americium fuel instead of conventional types of nuclear fuel - uranium and/or MOX-fuel. The advantages of implementation of this approach to transmutation as compared with traditional ones are fairly obvious. Thus, if, for instance, a reactor loaded with uranium or MOX-fuel is used for transmutation, then, in addition to burning «foreign» minor actinides, it will simultaneously be breeding «its own» long-lived nuclides. In the case of fuel composed of some minor actinides, it will be only incinerating «its own» inventory. Analysis demonstrated that only a fast reactor must be used for the purpose, which is associated with special properties of neutron capture and fission cross-sections for minor actinides compared to nuclides in the composition of conventional fuel. The results of calculations demonstrated fairly high rate of americium transmutation in reactor loaded with americium fuel. Implemented studies of americium transmutation revealed an interesting effect. After initiation of irradiation the value of keff first increases and then begins to decrease. The explanation is associated with accumulation of nuclides additionally contributing in the multiplication factor as compared with fresh americium. An important argument in favor of reactor load with americium fuel is that by burning long-lived waste we produce electrical energy. The problem for nuclear reactor loaded with uranium or with MOX-fuel is, as well, that transmutation impairs reactor economy and its performance parameters. Designing reactor core with americium fuel remains to be problematic. The problem of high heat dissipation of such fuel must be addressed in the first place.