Персона: Терехова, Анна Михайловна
Загружается...
Email Address
Birth Date
Научные группы
Организационные подразделения
Организационная единица
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.
Статус
Фамилия
Терехова
Имя
Анна Михайловна
Имя
6 results
Результаты поиска
Теперь показываю 1 - 6 из 6
- 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.
- 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.
- ПубликацияТолько метаданныеResearch reactor model for isotope production based on the design of VVER-440 reactors(2020) Terekhova, A.; Mahdi, A.; Zykova, R.; Терехова, Анна Михайловна© Carl Hanser Verlag, München.The following work is an attempt to develop a model research reactor based on VVER-440 technologies, primarily for the production of radioisotopes used in nuclear medicine procedures. The article describes the basic design features of the model 10 MW multipurpose VVR reactor, including the features of reactor fuel, core, and related structures. A comparative analysis of targets for maximizing 99Mo production is also presented.
- 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.