RU93035658A - PASSIVE HEAT REMOVAL SYSTEM FROM NUCLEAR POWER PLANT - Google Patents

PASSIVE HEAT REMOVAL SYSTEM FROM NUCLEAR POWER PLANT

Info

Publication number
RU93035658A
RU93035658A RU93035658/25A RU93035658A RU93035658A RU 93035658 A RU93035658 A RU 93035658A RU 93035658/25 A RU93035658/25 A RU 93035658/25A RU 93035658 A RU93035658 A RU 93035658A RU 93035658 A RU93035658 A RU 93035658A
Authority
RU
Russia
Prior art keywords
power plant
nuclear power
heat exchanger
jet pump
removal system
Prior art date
Application number
RU93035658/25A
Other languages
Russian (ru)
Other versions
RU2037893C1 (en
Inventor
К.И. Сопленков
В.Г. Селиванов
Ю.Н. Филимонцев
Б.И. Нигматулин
В.В. Бредихин
Е.И. Трубкин
Е.З. Емельяненко
А.А. Козенюк
М.А. Найденышев
В.Н. Крушельницкий
В.А. Викин
В.С. Зарубаев
В.Ф. Лоскутов
В.А. Коровкин
Н.А. Фридман
А.Г. Корниенко
В.М. Беркович
Л.И. Гуревич
В.Г. Федоров
М.Ф. Рогов
Г.И. Бирюков
Original Assignee
К.И. Сопленков
Filing date
Publication date
Application filed by К.И. Сопленков filed Critical К.И. Сопленков
Priority to RU9393035658A priority Critical patent/RU2037893C1/en
Priority claimed from RU9393035658A external-priority patent/RU2037893C1/en
Application granted granted Critical
Publication of RU2037893C1 publication Critical patent/RU2037893C1/en
Publication of RU93035658A publication Critical patent/RU93035658A/en

Links

Claims (1)

Изобретение относится к атомной энергетике и предназначено для отвода теплоты от теплоисточника ядерной энергоустановки. Предлагаемая система работает надежно и стабильно. Система содержит теплообменник и контур циркуляции теплоносителя ядерной энергоустановки, параллельно которому подключен струйный насос в виде инжектора-конденсатора, вход струйного насоса по инжектируемой среде соединен с выпускным каналом теплообменника, впускной канал теплообменника соединен с теплоисточником в области, предназначенной для конденсата, на выходном трубопроводе струйного насоса установлен обратный клапан, между которым и струйным насосом помещен конденсационный модуль, с помощью которого осуществляется запуск системы конденсат из теплоисточника (парогенератора или реактора) поступает в теплообменник, охлаждается в нем и подается в сопло инжектируемого потока струйного насоса.The invention relates to nuclear energy and is intended to remove heat from the heat source of a nuclear power plant. The proposed system works reliably and stably. The system contains a heat exchanger and a coolant circulation loop of a nuclear power plant, in parallel with which a jet pump in the form of an injector-condenser is connected, the inlet of the jet pump is connected to the outlet channel of the heat exchanger through the injected medium, the inlet channel of the heat exchanger is connected to the heat source in the area for condensate, at the outlet pipe of the jet a check valve is installed on the pump, between which a condensation module is placed with the jet pump, with the help of which In the system, condensate from the heat source (steam generator or reactor) enters the heat exchanger, is cooled in it and fed into the nozzle of the injected stream of the jet pump.
RU9393035658A 1993-07-22 1993-07-22 System for passive abstraction of heat from nuclear power plant RU2037893C1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
RU9393035658A RU2037893C1 (en) 1993-07-22 1993-07-22 System for passive abstraction of heat from nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
RU9393035658A RU2037893C1 (en) 1993-07-22 1993-07-22 System for passive abstraction of heat from nuclear power plant

Publications (2)

Publication Number Publication Date
RU2037893C1 RU2037893C1 (en) 1995-06-19
RU93035658A true RU93035658A (en) 1997-03-10

Family

ID=20144825

Family Applications (1)

Application Number Title Priority Date Filing Date
RU9393035658A RU2037893C1 (en) 1993-07-22 1993-07-22 System for passive abstraction of heat from nuclear power plant

Country Status (1)

Country Link
RU (1) RU2037893C1 (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2827997B1 (en) * 2001-07-24 2005-10-07 Framatome Anp METHOD AND DEVICE FOR SUPPLYING AT LEAST ONE STEAM GENERATOR FROM A PRESSURIZED WATER NUCLEAR REACTOR DURING REACTION STOPPING PERIODS
RU2626620C1 (en) * 2016-07-25 2017-07-31 Акционерное общество Инжиниринговая компания "АСЭ" Emergency system of boric acid solution supply to active zone of npp reactor
RU2631057C1 (en) * 2016-12-28 2017-09-18 федеральное государственное бюджетное образовательное учреждение высшего образования "Санкт-Петербургский государственный морской технический университет" (СПбГМТУ) System of passive removal of heat of reactor installation

Similar Documents

Publication Publication Date Title
KR100323398B1 (en) Combined Cycle Power Unit
JP3373771B2 (en) Waste heat recovery boiler
RU2346730C2 (en) Aggregate and method of co2 extraction
SU1755716A3 (en) Condenser cooling system of steam-turbine plants
IT8922553A1 (en) HEAT EXCHANGERS IN SERIES PARTICULARLY FOR A GAS TURBOMOTOR
MXPA03010652A (en) Device for cooling coolant in a gas turbine and gas and steam turbine with said device.
JPS5895295A (en) Water spray device by steam drive
CN1192030A (en) Drain system for nuclear power plant
RU93035658A (en) PASSIVE HEAT REMOVAL SYSTEM FROM NUCLEAR POWER PLANT
MY123730A (en) Method and configuration for deaerating a condensate
RU2276813C1 (en) Nuclear power plant and steam turbine
RU2037893C1 (en) System for passive abstraction of heat from nuclear power plant
SE9703426L (en) Device for cooling gases
US4236968A (en) Device for removing heat of decomposition in a steam power plant heated by nuclear energy
RU97120380A (en) STEAM GAS INSTALLATION
RU96116752A (en) ENERGY INSTALLATION
RU24748U1 (en) NUCLEAR POWER PLANT
RU2002321C1 (en) Passive residual-heat transfer system for nuclear reactor
JP3089151B2 (en) High pressure spray combustion device
RU2198346C2 (en) Ultrahigh pressure mixing heat exchanger for preheating feed water at atomic power station
RU2059945C1 (en) Heat generator
JPH02222880A (en) Cooling equipment of nuclear power plant
RU2163670C1 (en) Steam-and-water power and heat generating plant
RU2179289C2 (en) Heat exchanger
JPS58190690A (en) Power generating plant having sidestream type condensed water purification system