Кафедра "Парогенераторобудування"

Постійне посилання колекціїhttps://repository.kpi.kharkov.ua/handle/KhPI-Press/4698

Офіційний сайт кафедри http://web.kpi.kharkov.ua/pgs

Від 1938 року кафедра має назву "Парогенераторобудування", первісна назва – кафедра парових турбін.

Кафедра парових турбін у 1930 році виділилися як самостійна зі складу кафедри теплотехніки, на якій професори Георгій Федорович Бураков, Петро Матвійович Мухачов і С. Н. Семихватов забезпечували підготовку інженерів парових котлів. Уперше курс парових котлів почав читати в інституті в 1888 році професор Олексій Іванович Предтеченський.

Кафедра входить до складу Навчально-наукового інституту енергетики, електроніки та електромеханіки Національного технічного університету "Харківський політехнічний інститут".

У складі науково-педагогічного колективу кафедри працюють: 1 доктор технічних наук, 4 кандидати технічних наук; 1 співробітник має звання професора, 4 – доцента.

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20192

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Автор: search.filters.author.Romashov, YuryМістить файли: Так

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  • Ескіз
    Документ
    Approximate estimates of the temperature state of ceramic nuclear fuel in cylindrical fuel elements and the influence of processes and parameters of a nuclear reactor core
    (Національний технічний університет "Харківський політехнічний інститут", 2019) Romashov, Yury; Chibisov, Dmytro
    The approximate mathematical model of the temperature state of ceramic nuclear fuels in cylindrical fuel elements was proposed in the form of linear ordinary differential equation and the boundary conditions. The theory of heat conduction and assumptions about the axial symmetry and absence of heat flows along axis of fuel element, which allow to simplify the common equations in cylindrical coordinates, are the basis of the proposed simplified mathematical model for approximate estimating the temperature state of the nuclear fuel. The intensity of volume heat sources in fuel element was taken into account by using the average values corresponding with the heat power and the structural characteristics of a nuclear reactor core. The conception about the heat transfer coefficient was used for modeling interaction between the fuel and the heat carrier. This heat transfer coefficient depends on characteristic sizes and heat conductions of constituted materials of the fuel element and allows to estimate influence of these on the temperature state of the nuclear fuel. The analytical solution for the temperature of a ceramic fuel in cylindrical fuel elements was obtained and was used for researching. It was shown that the heat conductivity of the fuel has significantly influences both the average temperature and the difference between the inner and outer temperatures in the fuel pellet. At the same time, other parameters have significant influence only on the average temperature of the fuel pellet. Due to these, it is necessary to consider the temperature dependence of the thermal conductivities of the materials constituted the fuel elements for more precisely estimations the temperature state of the fuel pellets, which will lead to nonlinear equations will required the numerical methods for their solving.
  • Ескіз
    Документ
    Estimating workability of steam boilers superheaters considering with the high temperature creep and uniform chemical corrosion
    (Національний технічний університет "Харківський політехнічний інститут", 2019) Yefimov, Aleksander; Romashov, Yury; Kavertsev, Valerii
    It is proposed theoretical estimating workability of steam boilers superheaters on the base of considering the influence of a high-temperature uniform chemical corrosion on of a high-temperature creep of superheater pipes on account of stresses redistributions the pipes walls due to their thickness decreasing. The high-temperature uniform chemical corrosion is presented by the well-known time and temperature depend-ences of the height of damaged material. The high-temperature creep is considered using the well-known incremental-type theory taking into account the Cachanov-Rabotnov scalar damage parameter. It is proposed the mathematical model of state of superheaters pipes in the form of initial-boundary-value problem in the domain with the moving boundary. The differential equations, initial and boundary conditions of that problem are corresponded to the well-known in the theory of high-temperature creep. Moving of the boundary is corresponded to the well-known time dependence of the height of damaged material due to the high-temperature uniform chemical corrosion. Although, the used theory of creep and the used regularities of uniform corrosion are well-known separately, considering the influence of uniform corrosion on the creep is the complicated problem due to the moving boundary in the corresponded initial-boundary-value problem. It is shown, that the spatial variable replacement allows to reduce the proposed initial-boundary-value problem with the moving boundary to the initial-boundary-value problem with the fixed normed boundary, that allows to simplify numerical solving of the considered problem. The method of lines is discussed for solving the initial-boundary-value problem, representing the mathematical model of the state of pipes of superheaters.