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.

Переглянути

Зараз показуємо 1 - 20 з 200

Application of interval statistics methods for power station equipment diagnostics in conditions of initial data uncertainty
(Polska Akademia Nauk Oddzial w Lublinie, 2012) Efimov, Aleksander; Potanina, Tatiana
In article principles of automated diagnostics system construction of the power units equipment and planning of repairs are investigated. The model constructed on the basis of interval data statistics of diagnostic functions is presented.
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.
Assessments of opportunities of numerical methods of grids for solving the time-dependent thermal conduction problems of ceramic nuclear fuel
(NTU "KhPI", 2018) Yefimov, A. V.; Romashov, Yu. V.; Yesypenko, T. A.; Chibisov, D. O.
Basic bases of calculations and optimization of NPP power unit equipment parameters methods of mathematical modelling
(Національний технічний університет "Харківський політехнічний інститут", 2021) Yefimov, Olexander Vyacheslavovych; Ilchenko, Boris Samuilovich; Tiutiunyk, Larysa Ivanivna; Harkusha, Tetyana Anatoliivna; Yesipenko, Tetyana Oleksiivna; Motovilnik, Anastasiia Vadimovna
The materials of the article consider the optimization of certain parameters and characteristics of the equipment of NPP power units, which are closely related to the processes of their design and construction. Modern NPP power units are complex technical systems. They include a set of interconnected equipment for different technological purposes, which ensures the performance of power units of a complex function of electricity production and heat of the specified quality and according to a given load schedule. Complete mathematical models of the functional state of steam turbine power units are characterized by a large number of nonlinear connections and contain implicit functions. This complicates their widespread use to solve problems of systematic analysis of the quality of operation of power units. The aim of the work is to analyze the basic theoretical foundations, methods and approaches to the calculation and optimization of the parameters of the equipment of NPP power units by methods of mathematical modeling. The solution of the problem of optimization of NPP power unit parameters includes the following stages: selection of optimality criteria (objective functions); development of a system of interconnected mathematical models in accordance with the required hierarchical level of optimization research; selection of computational methods and optimization algorithms. Taking into account the above methodological provisions and approaches increases the efficiency of mathematical modeling to solve problems of calculations and optimization of NPP power unit parameters.
Classification of nuclear NPP reactors
(Національний технічний університет "Харківський політехнічний інститут", 2023) Yefimov, Olexander Vyacheslavovych; Tiutiunyk, Larysa Ivanivna; Kavertsev, Valery Leonidovich; Harkusha, Tetyana Anatoliivna; Sydorkin, Igor Dmytrovych
The article deals with the classification of NPP nuclear reactors. A nuclear reactor is a device in which a chain reaction of nuclear fission of heavy elements uranium, plutonium, and thorium takes place, which controls and maintains itself. The possibility of such a reaction is ensured by the fact that each act of nuclear fission produces two or three neutrons capable of causing the fission of other nuclear fuel nuclei loaded into the reactor. In the reactor, simultaneously with the nuclear fission process, there is always, firstly, the absorption of neutrons by materials located in the active zone, and, secondly, the outflow of neutrons from the active zone of the reactor. These two factors make it possible to regulate the nuclear fission process so that the number of neutrons in the active zone and the number of acts of fission per unit of time are constant. Nuclear reactors are very diverse in terms of their parameters, purpose, design and a number of other features. Nuclear reactors can be classified according to the following main distinguishing features: the amount of neutron energy that causes nuclear fission; by type of retarder; according to the type and parameters of the coolant; by constructive execution; according to the compositional decision; by appointment. At nuclear power plants, nuclear reactors are used to generate electrical and thermal energy. At nuclear power plants, they are used to generate thermal energy for the purpose of heating and industrial heat supply. In ship power plants, they are used as sources of thermal, mechanical and electrical energy.
Computer-integrated components of the automated decision-making support system for operational and maintenance personnel of nuclear power plant units with WWER
(Національний технічний університет "Харківський політехнічний інститут", 2019) Yefimov, Аleksandr Vyacheslavovych; Yesypenko, Tetyana Oleksiivna; Harkusha, Tetyana Anatoliivna; Kavertsev, Valery Leonidovich ; Berkutova, Tetyana Ivanivna
The purpose of this article is to describe the results of the research aimed at developing computer-integrated components of one of the ADMSS variants for operational and maintenance personnel of NPP units according to the criterion of technical and economic efficiency, taking into account the diagnostics of the technical equipment state based on the simulation model describing by means of up-to-date mathematical methods the technological processes in the main and auxiliary equipment of power units using up-to-date mathematical methods at the level of detailing, corresponding to their principle and deployed thermal schemes. The results of studies aimed at the development of computer-integrated components of the automated decision-making support system (ADMSS) for operational and maintenance personnel of NPP units by the criterion of technical and economic efficiency, taking into account the diagnostics of the state of the power unit equipment, are presented. The general structure of the software package interaction for the analysis of the performance and parameter diagnostics of NPP units with WWER has been developed. When creating the software package, the integrated programming environment Microsoft Visual Studios was used. The structure of the program block for the parameter diagnostics of the equipment of nuclear power units is presented. The main types of problems arising during the operation of NPP units with WWER, that can be solved with the help of the developed ADMSS are considered, and a form for presenting the results to the operational and maintenance personnel of power units is proposed. Developed on the basis of the described computer-integrated components, the automated decision-making support system for the operational and maintenance personnel of NPP power units can be used to solve a wide range of problems arising in the practice of short-, medium- and long-term control of the operation modes of power unit systems and equipment, including obtaining operational (energy) characteristics of power unit systems and equipment, optimizing operation modes and parameters, diagnosing and forecasting technical state of power equipment, predicting the amount of electrical and thermal energy generated by a power unit, as well as optimizing NPP repair cycles.
Construction materials of active zones of new generation nuclear reactors
(Національний технічний університет "Харківський політехнічний інститут", 2023) Yefimov, Olexander; Pylypenko, Mykola; Tiutiunyk, Larysa; Harkusha, Tetyana; Yesipenko, Tetyana; Motovilnik, Anastasiia
The materials of the article consider the analysis of construction materials of active zones of new generation nuclear reactors. The analysis reflects general ideas about the development of reactor technologies: in the 1950s and 1960s, the first generation of reactors was created; in the early 1970s, the operation of industrial reactors began - reactors of the second generation: pressurized water reactors (WWER, PWR), boiling water reactors (RBMK, BWR), heavy water reactors (CANDU), as well as gas-cooled reactors (AGR). Further development of some types of reactors made it possible to create reactors of the third generation in the 1980s. Priority when choosing directions of development in the category of revolutionary projects should have proposals capable of bringing a new quality to solving the problems of the nuclear energy industry of the future. Promising reactors have advantages in economy, safety, reliability and non-proliferation of nuclear materials. The effectiveness and reliability of structural materials are determined by the totality of changes in the characteristics of the materials as a result of the entire complex of phenomena occurring in them in the field of irradiation, in connection with the changing parameters and operating conditions. The use of high-purity metals as initial components of new structural materials and the development or optimization of their smelting technologies should ensure the required level of characteristics and properties of products made from them. The implementation of these concepts should be ensured by the development of new structural materials: ferritic-martensitic and austenitic steels, nickel and other new alloys.
Energy and environmental environment
(Національний технічний університет "Харківський політехнічний інститут", 2019) Tyutyunik, L.; Yefimov, A.; Ivanova, L.; Kasilov, V.
Energy saving technologies
(Лідер, 2021) Tiutiunyk, L. I.; Kasilov, V. I.; Ivanova, L. A.
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.
Flue gas purification from sulfur
(Національний технічний університет "Харківський політехнічний інститут", 2020) Tyutyunik, L.; Ivanova, L.; Kasilov, V.
Methods and approaches to simulation, diagnostics, forecasting equipment state and optimization of robot modes of NPP power units
(Національний технічний університет "Харківський політехнічний інститут", 2021) Yefimov, Olexander Vyacheslavovych; Kavertsev, Valery Leonidovich; Potanina, Tetiana Volodymyrivna; Harkusha, Tetyana Anatoliivna; Tiutiunyk, Larysa Ivanivna; Motovilnik, Anastasiia Vadimovna
Nuclear power plants are the basis of energy in many countries of the world, which determines the pace of their economic development. At the same time, they as complex technological systems are objects of the increased technogenic danger. Therefore, ways to increase the reliability, safety and efficiency of NPP power equipment have already been developed and continue to be developed, which are largely based on diagnostic procedures. During the operation of power equipment, especially during its long period, its technical characteristics, and, consequently, the parameters of technological processes, change under the influence of external factors and as a result of wear, or even destruction, of individual structural elements. Changing the characteristics of the equipment usually leads to a decrease in the level of adequacy and to the loss of conformity of mathematical expressions in the models of the content of the processes described by them.The materials of the article consider the identification of mathematical models of NPP power unit equipment in the process of parametric diagnostics. Ways to increase the reliability, safety and efficiency of NPP power equipment have been developed and continue to be developed, which are largely based on diagnostic procedures. The use of the iterative process to find the values of the identified parameters can be used to identify mathematical models of technological processes in NPP power equipment, which increases the adequacy of models and the reliability of diagnostic conclusions in solving parametric diagnostic problems.
Methods for optimizing the parameters of the equipment of NPP power units operating as part of energy systems
(Національний технічний університет "Харківський політехнічний інститут", 2022) Yefimov, Olexander Vyacheslavovych; Yesypenko, Tetyana Oleksiivna; Harkusha, Tetyana Anatoliivna
Methods of sulfur protection of fuels prior to their use in boilers
(Національний технічний університет "Харківський політехнічний інститут", 2020) Tyutyunik, L.; Ivanova, L.; Kasilov, V.
Methods that allow simultaneously to reduce emissionsoxides of nitrogen and sulfur dioxide
(Національний технічний університет "Харківський політехнічний інститут", 2019) Tyutyunik, L.; Yefimov, A.; Ivanova, L.; Kasilov, V.
Modeling npp power unit steam turbine installation steam separatorsuperheater temperature characteristics by interval analysis methods
(Національний технічний університет "Харківський політехнічний інститут", 2020) Potanina, Tetiana Volodymyrivna; Yefimov, Olexander Vyacheslavovych; Khavin, G. L.
The determination of the temperature characteristics of one of the significant elements of the wet-steam turbines of nuclear power units – the steam separator-superheater is considered: namely the construction of the dependence of the temperature of the heated steam at the outlet of the second stage on the changing load of the power unit. Modeling is carried out taking into account the error limitation without reliable information about its distribution. To evaluate the coefficients of empirical dependence, constructed according to the results of experimental data, it is proposed to use numerical methods of interval analysis. The interval approach allows building a refined tube, guaranteed to contain acceptable dependences of the temperature of the heated steam on the electric power of the power unit. In a situation of data uncertainty and limited errors, numerical methods of interval analysis allow creating models of processes and equipment of NPP units with the maximum possible correspondence to a real object.
Nature of the demand
(Національний технічний університет "Харківський політехнічний інститут", 2022) Tiutiunyk, Larysa Ivanivna; Kasilov, V.; Ivanova, L.
A set of programs for analyzing technical and economic efficiency of NPP power units
(ТОВ "Планета-Прінт", 2021) Yefimov, Olexander Vyacheslavovych; Tiutiunyk, Larysa Ivanivna; Kavertsev, V. L.; Harkusha, Tetyana Anatoliivna
Temperature characteristics of superheater-separators in nuclear power plant units with the capacity of 1000 Mw
(ТОВ "Планета-Прінт", 2021) Yefimov, Olexander Vyacheslavovych; Potanina, Tetiana Volodymyrivna; Yesypenko, Tetyana Oleksiivna; Harkusha, Tetyana Anatoliivna
Автоматизація процесу визначення експлуатаційних характеристик парогенераторів АЕС з ВВЕР-1000 за допомогою комп'ютерного моделювання
(НТУ "ХПІ", 2013) Єфімов, Олександр В'ячеславович; Меньшикова, Олена Дмитрівна; Кухтін, Дмитро Ігорович