A nuclear steam-Braton combined cycle power generation system

A combined cycle power generation and Brayton cycle technology, applied in steam application, steam engine installation, combined combustion mitigation, etc., can solve problems such as unfavorable atmospheric or marine ecological balance, reduce energy utilization efficiency of power station, affect ecological environment, etc., to improve energy The effect of utilizing efficiency, convenient peak regulation, and reducing the power of the power generation system

Active Publication Date: 2020-04-10
XI AN JIAOTONG UNIV
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  • Description
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Problems solved by technology

[0004] The waste heat generated by the reactor during the power cycle is generally discharged to the atmosphere or the ocean environment. On the one hand, it will cause energy loss and reduce the overall energy utilization efficiency of the power station; on the other hand, it will affect the ecological environment, which is not conducive to the ecological balance of the atmosphere or ocean.

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  • A nuclear steam-Braton combined cycle power generation system

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Embodiment Construction

[0021] The present invention will be described in detail below in conjunction with the accompanying drawings.

[0022] A nuclear steam-Brayton combined cycle power generation system (main system) of the present invention includes a nuclear reactor subsystem, an air Brayton cycle subsystem, a gas subsystem and a waste heat steam cycle subsystem, such as figure 1 shown.

[0023] Wherein, the nuclear reactor subsystem 1 includes at least one reactor core and a reactor pressure vessel, as well as a primary air heat exchanger 2 and a secondary air heat exchanger 3 . According to the characteristics of the reactor type, it can include primary or secondary energy transfer devices, namely intermediate heat exchangers and secondary loops. The reactor coolant outlet 1.1 is respectively connected with the primary side inlet 2.1 of the primary air heat exchanger and the primary side inlet 3.1 of the secondary air heat exchanger. The coolant releases heat in the air heat exchanger to heat...

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Abstract

The invention discloses a nuclear energy steam-Brayton combined cycle power generation system which comprises a nuclear reactor subsystem, an air Brayton cycle subsystem, a combustion subsystem and awaste heat steam cycle subsystem. Energy of the system can be independently provided by a reactor or be provided by a reactor and fuel gas in a combined manner, and a power cycle of the system is a combined cycle composed of a Brayton top cycle and a steam bottom cycle. The combustion subsystem can be started according to the power requirement of a main system and is connected into the air Braytoncycle through a control valve so as to meet the requirement of power increase during the period of the peak demand for electricity; and an exhaust valve is arranged in the air Brayton cycle, and high-temperature air can be directly discharged to the steam bottom cycle so as to meet the requirement of power reduce during the period of the valley demand for electricity. A waste heat steam generatoris adopted by the steam bottom cycle, waste heat of exhausted gas of the Brayton cycle can be further recycled to generate steam, and therefore the energy utilization rate of the whole system is increased.

Description

technical field [0001] The invention relates to a nuclear power generation system, in particular to a steam-Brayton combined cycle power generation system combining nuclear power and gas. Background technique [0002] The Brayton cycle, also known as the gas turbine cycle, uses air as the main working medium, and completes the cycle through pressure boost, combustion temperature rise, expansion work, constant pressure heat release, and converts the thermal energy of high-temperature gas into mechanical energy. With the development of reactor technology, a new generation of reactors can provide higher core outlet temperatures than conventional PWRs. For example, the outlet temperature of traditional pressurized water reactors is usually around 320 degrees Celsius, while the design outlet temperature of the new generation of molten salt reactors is generally 650 to 700 degrees Celsius, and the design outlet temperature of high temperature gas-cooled reactors is 750 to 950 degr...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): F01K23/10F01K17/02F01K13/00F01D15/10
CPCF01D15/10F01K13/00F01K17/02F01K23/10Y02E20/16
Inventor 张大林李林峰田文喜秋穗正苏光辉
Owner XI AN JIAOTONG UNIV
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