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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  • Ескіз
    Документ
    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.
  • Ескіз
    Документ
    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.