Secondary reheating power generation system based on ultra-supercritical parameters of high-temperature gas cooled reactor

Abstract

The invention discloses a secondary reheating power generation system for ultra-supercritical parameters of a high-temperature gas cooled reactor. The secondary reheating power generation system comprises a reactor, a steam generator, a primary steam reheater, a secondary steam reheater, a steam turbine ultrahigh-pressure cylinder, a steam turbine high-pressure cylinder, a steam turbine intermediate-pressure cylinder, a steam turbine low-pressure cylinder and a condenser, a gas outlet of the reactor is respectively connected with gas side inlets of the steam generator, the primary steam reheater and the secondary steam reheater; gas side outlets of the steam generator, the primary steam reheater and the secondary steam reheater are connected with a gas inlet of the reactor; a steam side outlet of the steam generator is sequentially connected with a steam turbine ultrahigh-pressure cylinder, a steam turbine high-pressure cylinder, a steam turbine intermediate-pressure cylinder, a steam turbine low-pressure cylinder, a condenser and a water side inlet of the steam generator. A steam exhaust outlet of the turbine ultrahigh-pressure cylinder is connected with a steam side inlet of the primary steam reheater, a steam side outlet of the primary steam reheater is connected with an inlet of the turbine high-pressure cylinder, a steam exhaust outlet of the turbine high-pressure cylinder is connected with a steam side inlet of the secondary steam reheater, and a steam side outlet of the secondary steam reheater is connected with an inlet of the turbine intermediate-pressure cylinder. The system can increase the steam temperature, reduce the final-stage humidity and effectively improve the power generation efficiency.

Description

Technical Field

[0001] The invention relates to the technical field of nuclear power generation, and in particular to a secondary reheat power generation system for ultra-supercritical parameters of a high-temperature gas-cooled reactor. Background Art

[0002] As one of the main power generation technologies in the world, nuclear power generation technology has long been a key technology for the development of major countries. With the increasingly stringent international requirements for greenhouse gas (CO2) emissions, nuclear energy, as one of the main clean energy sources, has once again ushered in an important development opportunity. As the fourth-generation nuclear power generation technology, high-temperature gas-cooled reactors have become a hot spot for research and development in major economic countries due to their inherent safety, high power generation efficiency and the ability to carry out process heat applications.

[0003] However, due to the great conservatism of existing steam generators (using linear elastic methods for material fatigue-creep analysis), only subcritical superheated steam can be produced through heat exchange, and the parameters of the heat exchange tubes and steam are difficult to further improve, thus limiting the further improvement of power generation efficiency.

[0004] With the development of technology, high temperature gas-cooled reactor technology will develop in the direction of large capacity and high parameters to improve the cycle efficiency of the unit. When the unit parameters are increased to ultra-supercritical, the increase in initial pressure will lead to an increase in the humidity of the last stage of the turbine, increasing the wet steam loss. At the same time, excessive exhaust steam humidity will also affect the life of the last few stages of blades and affect the safe operation of the unit. Summary of the invention

[0005] The purpose of the present invention is to provide a secondary reheat power generation system with ultra-supercritical parameters of a high-temperature gas-cooled reactor in response to the demand for high-temperature gas-cooled reactor units to develop in the direction of large capacity and high parameters to improve efficiency, which can increase steam temperature, reduce terminal humidity, and effectively improve power generation efficiency.

[0006] In order to achieve the above object, the present invention adopts the following technical solutions:

[0007] A secondary reheat power generation system for ultra-supercritical parameters of a high-temperature gas-cooled reactor, comprising a reactor, a steam generator, a primary steam reheater, a secondary steam reheater, a steam turbine ultra-high pressure cylinder, a steam turbine high pressure cylinder, a steam turbine intermediate pressure cylinder, a steam turbine low pressure cylinder and a condenser;

[0008] The gas outlet of the reactor is connected to the gas side inlets of the steam generator, the primary steam reheater and the secondary steam reheater respectively, and the gas side outlets of the steam generator, the primary steam reheater and the secondary steam reheater are connected to the gas inlet of the reactor;

[0009] The steam side outlet of the steam generator is connected to the water side inlet of the steam turbine ultra-high pressure cylinder, the steam turbine high pressure cylinder, the steam turbine intermediate pressure cylinder, the steam turbine low pressure cylinder, the condenser and the steam generator in sequence; the exhaust outlet of the steam turbine ultra-high pressure cylinder is connected to the steam side inlet of the primary steam reheater, the steam side outlet of the primary steam reheater is connected to the inlet of the steam turbine high pressure cylinder, the exhaust outlet of the steam turbine high pressure cylinder is connected to the steam side inlet of the secondary steam reheater, and the steam side outlet of the secondary steam reheater is connected to the inlet of the steam turbine intermediate pressure cylinder.

[0010] Preferably, a flow valve is provided between the connection outlet of the reactor and the gas side inlet of the steam generator, the primary steam reheater and the secondary steam reheater, respectively.

[0011] Preferably, the steam extraction outlets of the turbine ultra-high pressure cylinder, the turbine high pressure cylinder, the turbine intermediate pressure cylinder and the turbine low pressure cylinder are respectively connected to a number of feed water heaters, the steam extraction outlets of the turbine ultra-high pressure cylinder, the turbine high pressure cylinder, the turbine intermediate pressure cylinder and the turbine low pressure cylinder are connected to the steam side of the feed water heater, the water side inlet of the feed water heater is connected to the condenser outlet, and the water side outlet of the feed water heater is connected to the water side inlet of the steam generator.

[0012] Furthermore, the number of steam extraction outlets of the steam turbine ultra-high pressure cylinder is one, the number of steam extraction outlets of the steam turbine high pressure cylinder is two, the number of steam extraction outlets of the steam turbine intermediate pressure cylinder is three, and the number of steam extraction outlets of the steam turbine low pressure cylinder is four, and each steam extraction outlet is connected to a feed water heater.

[0013] Preferably, the gas at the gas outlet of the reactor is helium.

[0014] Preferably, the feed water from the condenser is heated in sequence by the extraction steam from the turbine low-pressure cylinder, turbine intermediate-pressure cylinder, turbine high-pressure cylinder and turbine ultra-high-pressure cylinder on the water side of the feed water heater, and then enters the water side of the steam generator.

[0015] Compared with conventional technologies, the present invention has the following beneficial effects:

[0016] After the parameters of the high-temperature gas-cooled reactor unit of the present invention are increased to ultra-supercritical, the humidity of the last stage of the steam turbine increases, and the wet steam loss increases. The present invention adds two steam reheaters after the reactor. After the superheated steam enters the ultra-high pressure cylinder and the high pressure cylinder of the steam turbine, and drives the rotor to rotate to generate power, the steam at the outlet of the ultra-high pressure cylinder and the high pressure cylinder of the steam turbine is reheated, and then enters the medium pressure cylinder of the steam turbine to generate power, which can effectively improve the power generation efficiency.

[0017] Furthermore, the flow valve can adjust the gas flow entering the steam heater and the steam reheater according to the actual steam flow to ensure consistent outlet temperature. BRIEF DESCRIPTION OF THE DRAWINGS

[0018] Figure 1 It is a schematic diagram of the system structure of the present invention;

[0019] Among them: 1-reactor; 2-steam generator; 3-primary steam reheater; 4-secondary steam reheater; 5-steam turbine ultra-high pressure cylinder; 6-steam turbine high pressure cylinder; 7-steam turbine intermediate pressure cylinder; 8-steam turbine low pressure cylinder; 9-first feedwater heater; 10-second feedwater heater; 11-third feedwater heater; 12-fourth feedwater heater; 13-fifth feedwater heater; 14-sixth feedwater heater; 15-seventh feedwater heater; 16-eighth feedwater heater; 17-ninth feedwater heater; 18-tenth feedwater heater; 19-condenser; 20-flow valve. DETAILED DESCRIPTION

[0020] The present invention is further described in detail below in conjunction with the accompanying drawings:

[0021] like Figure 1 As shown, the secondary reheat power generation system for ultra-supercritical parameters of a high-temperature gas-cooled reactor according to the present invention includes a reactor 1, a steam generator 2, a primary steam reheater 3, a secondary steam reheater 4, a steam turbine ultra-high pressure cylinder 5, a steam turbine high pressure cylinder 6, a steam turbine intermediate pressure cylinder 7, a steam turbine low pressure cylinder 8, ten feed water heaters and a condenser 19.

[0022] The gas outlet of the reactor 1 is connected to the gas side inlets of the steam generator 2, the primary steam reheater 3 and the secondary steam reheater 4 respectively, and the gas side outlets of the steam generator 2, the primary steam reheater 3 and the secondary steam reheater 3 are connected to the gas inlet of the reactor 1. The gas at the gas outlet of the reactor 1 is helium.

[0023] A flow valve 20 is provided between the connection outlet of the reactor 1 and the gas side inlet of the steam generator 2, the primary steam reheater 3 and the secondary steam reheater 4. The flow valve 20 can adjust the gas flow entering the steam heater and the steam reheater according to the actual steam flow to ensure that the outlet temperature is consistent.

[0024] The steam side outlet of the steam generator 2 is connected in sequence to the steam turbine ultra-high pressure cylinder 5, the steam turbine high pressure cylinder 6, the steam turbine intermediate pressure cylinder 7, the steam turbine low pressure cylinder 8, the condenser 19, the steam sides of ten feed water heaters and the water side inlet of the steam generator 2; the exhaust outlet and the extraction outlet of the steam turbine intermediate pressure cylinder 7 are both connected to the inlet of the steam turbine low pressure cylinder 8.

[0025] A steam extraction outlet is provided on the steam turbine ultra-high pressure cylinder 5 , and the steam extraction outlet on the steam turbine ultra-high pressure cylinder 5 is connected to the steam side inlet of the first feed water heater 9 .

[0026] Two steam extraction outlets are arranged on the high-pressure cylinder 6 of the steam turbine, and the two steam extraction outlets on the high-pressure cylinder 6 of the steam turbine are connected to the steam side inlets of the second feed water heater 10 and the third feed water heater 11 respectively.

[0027] The turbine intermediate pressure cylinder 7 is provided with three steam extraction outlets, which are connected to the steam side inlets of the fourth feed water heater 12, the fifth feed water heater 13 and the sixth feed water heater 14 respectively.

[0028] The turbine low-pressure cylinder 8 is provided with four steam extraction outlets, which are connected to the steam side inlets of the seventh feedwater heater 15, the eighth feedwater heater 16, the ninth feedwater heater 17 and the tenth feedwater heater 18 respectively.

[0029] The high-temperature helium gas from the reactor 1 is divided into three streams, which enter the gas-side inlet of the steam generator 2, the primary steam reheater 3, and the secondary steam reheater 4 respectively to heat the steam, and then return to the reactor 1 to complete the cycle; the feed water from the condenser 19 enters the water-side inlet of the steam generator 2, absorbs the heat from the gas side of the steam generator 2 and becomes superheated steam, and after the superheated steam enters the super-high-pressure cylinder 5 of the steam turbine, it drives the rotor of the high-pressure cylinder 5 of the steam turbine to rotate and do work; the steam at the exhaust outlet of the super-high-pressure cylinder 5 of the steam turbine enters the steam-side inlet of the primary steam reheater 3 for reheating, and then enters the high-pressure cylinder 6 of the steam turbine to enter The steam at the exhaust outlet of the high-pressure cylinder 6 of the steam turbine enters the steam side inlet of the secondary steam reheater 4 for reheating, and then enters the intermediate-pressure cylinder 7 of the steam turbine to perform work. The steam at the exhaust outlet of the intermediate-pressure cylinder 7 of the steam turbine enters the low-pressure cylinder 8 of the steam turbine. The steam after the work of the low-pressure cylinder 8 of the steam turbine is discharged from the exhaust outlet, which is called exhaust steam. The exhaust steam is cooled by cooling water in the condenser 19 and condensed into water again. It is heated in turn by the extraction steam of the low-pressure cylinder 8 of the steam turbine, the intermediate-pressure cylinder 7 of the steam turbine, the high-pressure cylinder 6 of the steam turbine and the ultra-high-pressure cylinder 5 of the steam turbine on the water side of the ten feedwater heaters, and then enters the water side of the steam generator 2 to complete a cycle.

Claims

1. A secondary reheat power generation system for ultra-supercritical parameters of high temperature gas-cooled reactor, characterized in that: The invention comprises a reactor (1), a steam generator (2), a primary steam reheater (3), a secondary steam reheater (4), a steam turbine super-high pressure cylinder (5), a steam turbine high pressure cylinder (6), a steam turbine intermediate pressure cylinder (7), a steam turbine low pressure cylinder (8) and a condenser (19); the gas outlet of the reactor (1) is respectively connected to the gas side inlets of the steam generator (2), the primary steam reheater (3) and the secondary steam reheater (4); the gas side outlets of the steam generator (2), the primary steam reheater (3) and the secondary steam reheater (4) are connected to the gas inlet of the reactor (1); the steam generator ( The steam side outlet of the steam turbine (2) is connected in sequence to the steam turbine super-high pressure cylinder (5), the steam turbine high pressure cylinder (6), the steam turbine intermediate pressure cylinder (7), the steam turbine low pressure cylinder (8), the condenser (19) and the water side inlet of the steam generator (2); the exhaust steam outlet of the steam turbine super-high pressure cylinder (5) is connected to the steam side inlet of the primary steam reheater (3), the exhaust steam outlet of the steam turbine high pressure cylinder (6) is connected to the steam side inlet of the secondary steam reheater (4), the steam side outlet of the primary steam reheater (3) is connected to the inlet of the steam turbine high pressure cylinder (6), and the steam side outlet of the secondary steam reheater (4) is connected to the inlet of the steam turbine intermediate pressure cylinder (7).

2. The secondary reheat power generation system for ultra-supercritical parameters of high temperature gas-cooled reactor according to claim 1, characterized in that: A flow valve (20) is respectively provided between the connection outlet of the reactor (1) and the gas side inlet of the steam generator (2), the primary steam reheater (3) and the secondary steam reheater (4).

3. The secondary reheat power generation system for ultra-supercritical parameters of high temperature gas-cooled reactor according to claim 1, characterized in that: The steam extraction outlets of the steam turbine ultra-high pressure cylinder (5), the steam turbine high pressure cylinder (6), the steam turbine intermediate pressure cylinder (7) and the steam turbine low pressure cylinder (8) are respectively connected to a plurality of feed water heaters; the steam extraction outlets of the steam turbine ultra-high pressure cylinder (5), the steam turbine high pressure cylinder (6), the steam turbine intermediate pressure cylinder (7) and the steam turbine low pressure cylinder (8) are connected to the steam side of the feed water heater; the water side inlet of the feed water heater is connected to the outlet of the condenser (19); and the water side outlet of the feed water heater is connected to the water side inlet of the steam generator (2).

4. The secondary reheat power generation system for ultra-supercritical parameters of high temperature gas-cooled reactor according to claim 3, characterized in that: The number of steam extraction outlets of the steam turbine ultra-high pressure cylinder (5) is one, the number of steam extraction outlets of the steam turbine high pressure cylinder (6) is two, the number of steam extraction outlets of the steam turbine intermediate pressure cylinder (7) is three, and the number of steam extraction outlets of the steam turbine low pressure cylinder (8) is four, and each steam extraction outlet is connected to a feed water heater.

5. The secondary reheat power generation system for ultra-supercritical parameters of high temperature gas-cooled reactor according to claim 1, characterized in that: The gas at the gas outlet of the reactor (1) is helium.

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