Тепловий розрахунок високотемпературного парогенератора ядерної енергетичної установки ГТ-МГР з гвинтовими закрученими трубними пучками
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Дата
2018
ORCID
DOI
10.20998/2078-774X.2018.11.13
Науковий ступінь
Рівень дисертації
Шифр та назва спеціальності
Рада захисту
Установа захисту
Науковий керівник
Члени комітету
Видавець
НТУ "ХПІ"
Анотація
Розглянуто високотемпературний парогенератор ядерної енергетичної установки ГТ-МГР з використанням гелію в якості первинного теплоносія для виробництва електроенергії та водню. Розроблена математична модель для теплового розрахунку високотемпературного парогенератора з гвинтовими закрученими трубними пучками, завдяки якій було реалізовано п’ять різних методів розрахунку теплообміну при кипінні у вертикальній трубі, заснованих на експериментальних кореляційних залежностях та проведено оцінку залежності коефіцієнтів тепловіддачі двофазного потоку від величини масового витратного паровмісту.
This scientific paper is devoted to a thermal design of the high-temperature steam generator for the nuclear power plant GT-MGR of the fourth generation using helium as a primary heat carrier for the production of electric energy and hydrogen. The steam generator in question consists of the shell in the form of secondary circuit with the tube bundle of a small size as a secondary circuit with helical (coil-in-box) pipes that are arranged inside the shell in the form of tubular cylinders connected in parallel. A mathematical model of the steam generator for the NPP was constructed to give consideration to the boiling liquid flow in the vertical channel of an arbitrary shape with the heating along the entire length. The developed mathematical model allowed us to realize five different methods for the computation of heat exchange during the boiling in the vertical tube that are based on experimental correlation relationships. The obtained results showed that a peculiar maximum of the value of heat transfer coefficient for the two-phase flow exists when the methods of Chen and Gungor-Winterton are used. The behavior patterns of heat-transfer coefficients for the two-phase flow as a function of the value of mass consumed steam content were compared for the five different methods of the computation of heat exchange in the boiling liquid. The analysis showed that the average value of heat –transfer coefficients for the two-phase flow at 0.2 < х < 0, is in the range of 827500...37500 for all the methods in question except for the Steiner-Taborque method. A critical value of the mass consumed steam content was defined using Bias correlations.
This scientific paper is devoted to a thermal design of the high-temperature steam generator for the nuclear power plant GT-MGR of the fourth generation using helium as a primary heat carrier for the production of electric energy and hydrogen. The steam generator in question consists of the shell in the form of secondary circuit with the tube bundle of a small size as a secondary circuit with helical (coil-in-box) pipes that are arranged inside the shell in the form of tubular cylinders connected in parallel. A mathematical model of the steam generator for the NPP was constructed to give consideration to the boiling liquid flow in the vertical channel of an arbitrary shape with the heating along the entire length. The developed mathematical model allowed us to realize five different methods for the computation of heat exchange during the boiling in the vertical tube that are based on experimental correlation relationships. The obtained results showed that a peculiar maximum of the value of heat transfer coefficient for the two-phase flow exists when the methods of Chen and Gungor-Winterton are used. The behavior patterns of heat-transfer coefficients for the two-phase flow as a function of the value of mass consumed steam content were compared for the five different methods of the computation of heat exchange in the boiling liquid. The analysis showed that the average value of heat –transfer coefficients for the two-phase flow at 0.2 < х < 0, is in the range of 827500...37500 for all the methods in question except for the Steiner-Taborque method. A critical value of the mass consumed steam content was defined using Bias correlations.
Опис
Ключові слова
теплоносій, гелій, електроенергія, водень, модель математична, тепловіддача, nuclear power plant, high temperature steam generator, tubular bundle, thermal design
Бібліографічний опис
Доник Т. В. Тепловий розрахунок високотемпературного парогенератора ядерної енергетичної установки ГТ-МГР з гвинтовими закрученими трубними пучками / Т. В. Доник, О. О. Сафронова, М. Н. Парашар // Вісник Нац. техн. ун-ту "ХПІ" : зб. наук. пр. Сер. : Енергетичні та теплотехнічні процеси й устаткування = Bulletin of the National Technical University "KhPI" : coll. sci. papers. Ser. : Power and Heat Engineering Processes and Equipment. – Харків : НТУ "ХПІ", 2018. – № 11 (1287). – С. 78-82.