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

Abstract

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

[0002] Nuclear power generation technology, one of the primary power generation technologies worldwide, has long been a key developmental technology for major economies. With increasingly stringent international regulations on greenhouse gas (CO2) emissions, nuclear energy, as a major clean energy source, is once again facing significant development opportunities. High-temperature gas-cooled reactors (HTGRs), as fourth-generation nuclear power generation technology, are a hot research and development area for major economies due to their inherent safety, high power generation efficiency, and ability to utilize process heat.

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

[0004] As technology advances, high-temperature gas-cooled reactors (HTGRs) will move toward larger capacities and higher parameters to improve unit cycle efficiency. When unit parameters are raised to ultra-supercritical levels, the increased initial pressure will lead to increased humidity in the final stages of the turbine, increasing wet steam losses. Excessive exhaust steam humidity will also shorten the life of the final stages' blades, impacting the unit's safe operation. Utility Model Content

[0005] The purpose of this utility model 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-capacity and high-parameter development and efficiency improvement of high-temperature gas-cooled reactor units, which can increase steam temperature, reduce the humidity of the final stage, and effectively improve power generation efficiency.

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

[0007] A secondary reheat power generation system for a high-temperature gas-cooled reactor with ultra-supercritical parameters, 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 several feedwater 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 feedwater heater, the water side inlet of the feedwater heater is connected to the condenser outlet, and the water side outlet of the feedwater 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 low-pressure cylinder of the turbine, the intermediate-pressure cylinder of the turbine, the high-pressure cylinder of the turbine and the ultra-high-pressure cylinder of the turbine 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 beneficial effects of the present invention are:

[0016] After the parameters of the high-temperature gas-cooled reactor unit in this utility model are increased to ultra-supercritical, the humidity in the final stage of the steam turbine increases, resulting in greater wet steam losses. This utility model adds two steam reheaters after the reactor. After the superheated steam enters the ultra-high-pressure and high-pressure cylinders of the steam turbine, driving their rotors to rotate and generate power, the steam at the outlet of the ultra-high-pressure and high-pressure cylinders is reheated before entering the intermediate-pressure cylinder of the steam turbine to generate power, effectively improving power generation efficiency.

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

[0018] Figure 1 This is a schematic diagram of the system structure of the utility model;

[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 described in further detail below with reference to 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 described in 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. 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 installed between the connection outlet of reactor 1 and the gas-side inlet of steam generator 2, primary steam reheater 3, and secondary steam reheater 4. The flow valve 20 adjusts the gas flow entering the steam heater and steam reheater based on the actual steam flow to ensure consistent outlet temperatures.

[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] The steam turbine ultra-high pressure cylinder 5 is provided with a steam extraction outlet, which is connected to the steam side inlet of the first feed water heater 9 .

[0026] Two steam extraction outlets are provided 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 feedwater heater 10 and the third feedwater heater 11 respectively.

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

[0028] The low-pressure cylinder 8 of the steam turbine is provided with four steam extraction outlets, which are respectively 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.

[0029] The high-temperature helium coming out of 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. 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 to rotate and do work; the steam from the exhaust outlet of the super-high-pressure cylinder 5 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 The exhaust steam 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 of the exhaust steam of the intermediate-pressure cylinder 7 of the steam turbine enters the low-pressure cylinder 8 of the steam turbine. The steam after the low-pressure cylinder 8 of the steam turbine has performed work is discharged from the exhaust outlet and 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 high temperature gas cooled reactor ultra supercritical parameters, 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 ( 2) is connected in sequence to the steam side outlet of 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) and the water side inlet of the steam generator (2); the exhaust steam outlet of the steam turbine ultra-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); A flow valve (20) is respectively provided between the connection outlet of the reactor (1) and the gas side inlets of the steam generator (2), the primary steam reheater (3) and the secondary steam reheater (4).

2. The secondary reheat power generation system for high temperature gas-cooled reactor ultra-supercritical parameters 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 heaters. The water side inlet of the feed water heaters is connected to the outlet of the condenser (19). The water side outlet of the feed water heaters is connected to the water side inlet of the steam generator (2).

3. The secondary reheat power generation system for ultra-supercritical parameters of a high-temperature gas-cooled reactor according to claim 2, 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.

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

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