Nuclear power generation-steam supply system and method

Abstract

The invention particularly relates to a nuclear energy power generation-steam supply system which comprises a steam generator, a nuclear energy power generation circulation loop and a nuclear energy steam supply circulation loop. The steam generator generates nuclear power station secondary loop main steam and sends the main steam into the nuclear power generation circulation loop and the nuclear steam supply circulation loop; the nuclear power generation circulation loop works on main steam of a nuclear power station secondary loop to generate power, then generates first condensed water and sends the first condensed water back to the steam generator, and sends second condensed water back to the steam generator; the nuclear energy steam supply circulation loop heats industrial feed water through nuclear power station secondary loop main steam fed by the steam generator, and second condensed water and industrial steam are generated; a plurality of water return points of second condensed water are arranged in the nuclear power generation circulation loop; and a working medium pump and a desuperheater are arranged in the nuclear energy steam supply circulation loop. The invention further relates to a nuclear power generation-steam supply method. The temperature of industrial steam is adjusted, heat of steam extraction condensation water is recycled, and the nuclear energy steam supply heat efficiency is improved.

Description

Technical Field

[0001] The present invention relates to the technical field of comprehensive utilization of nuclear energy, and in particular to a nuclear power generation-steam supply system and method. Background Art

[0002] Nuclear energy steam supply has the inherent advantage of being zero-carbon and clean, and has gradually become the first choice for emerging industrial parks.

[0003] At present, nuclear energy steam supply adopts the solution of long-distance transmission of superheated steam to users. Under the condition that the steam parameters meet the user's requirements, the accumulated flow is used as the settlement data. The disadvantage of this solution is that once the steam quality exceeds the user's requirements, on the one hand, the user side needs to adjust the flow to adapt to the heat change, and on the other hand, the power plant side will lose more heat under the same settlement cost, which greatly affects the economic efficiency of the project.

[0004] In addition, the temperature and pressure of the condensate formed after the nuclear power unit extracts steam to heat the working fluid (hereinafter referred to as "extraction condensate") is relatively high, but for safety reasons, the extraction condensate is generally discharged into the condenser, and part of the heat is eventually taken away by seawater and not utilized, resulting in a certain amount of heat loss. The nuclear energy steam supply system has a self-balancing nature, and it is difficult to achieve the regulation of steam and extraction condensate temperature while ensuring the steam supply flow. Therefore, there is an urgent need for a nuclear power generation-steam supply system that can simultaneously regulate the steam temperature and recover the heat of extraction condensate to improve the thermal efficiency of nuclear energy steam supply. Summary of the invention

[0005] The object of the present invention is to provide a nuclear power generation-steam supply system, which can simultaneously adjust the industrial steam temperature and recover the heat of extracted steam condensate by reducing the system complexity and operating in a highly economical manner, thereby improving the thermal efficiency of nuclear steam supply.

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

[0007] A nuclear power generation-steam supply system, comprising a steam generator, a nuclear power generation circulation loop and a nuclear power steam supply circulation loop;

[0008] The steam generator is configured to absorb the heat generated by the primary circuit of the nuclear power plant, heat the first condensate and the second condensate sent back by the nuclear power generation circulation circuit, generate the main steam of the secondary circuit of the nuclear power plant and send it into the nuclear power generation circulation circuit and the nuclear steam supply circulation circuit;

[0009] The nuclear power generation cycle loop is configured to generate first condensate water for the main steam of the secondary circuit of the nuclear power plant sent into the steam generator after generating power; and to send the second condensate water sent into the nuclear power steam supply cycle loop back to the steam generator;

[0010] The nuclear energy steam supply circulation loop is configured to heat industrial feed water with the secondary loop main steam of the nuclear power plant fed by the steam generator to generate secondary condensate and industrial steam;

[0011] A plurality of return water points of the second condensate are arranged in the nuclear power generation circulation loop; according to the temperature and pressure of the second condensate, a return water point with a temperature and pressure closest to and lower than that of the second condensate is selected, and the second condensate is sent into the nuclear power generation circulation loop;

[0012] A working fluid pump and a desuperheater are provided in the nuclear energy steam supply circulation loop. The working fluid pump adjusts the industrial steam pressure, and the desuperheater adjusts the industrial steam temperature.

[0013] As one of the feasible ways, the nuclear power generation cycle loop includes a steam turbine, a generator, a condenser, a condensate pump, a low-temperature heater, a deaerator, a feed water pump and a high-temperature heater which are connected in sequence by pipelines, and the steam turbine and the high-temperature heater are respectively connected to the steam generator pipeline.

[0014] As one of the feasible ways, the nuclear energy steam supply circulation loop includes a desalted water tank, a working fluid pump, a preheater, an industrial evaporator, a superheater, a desuperheater and an industrial steam user; the preheater, the industrial evaporator and the superheater all include mutually isolated tube side paths and shell side paths;

[0015] The desalted water tank, working fluid pump, preheater shell side path, industrial evaporator shell side path, superheater shell side path, desuperheater and industrial steam users are connected by pipelines in sequence to form an industrial side loop; the preheater tube side path, industrial evaporator tube side path and superheater tube side path are connected by pipelines in sequence to form a heat source side loop;

[0016] The preheater tube side path is connected to the steam generator pipeline, and the superheater tube side path is respectively connected to the condenser, the deaerator, and the pipeline between the condensate pump and the low-temperature heater; a second regulating valve is provided on the pipeline connecting the superheater tube side path to the condenser, a third regulating valve is provided on the pipeline connecting the superheater tube side path to the pipeline between the condensate pump and the low-temperature heater, and a fourth regulating valve is provided on the pipeline connecting the superheater tube side path to the deaerator;

[0017] The outlet of the working fluid pump is connected to the water spray outlet pipeline of the desuperheater, and a first regulating valve is arranged on the pipeline connecting the outlet of the working fluid pump and the water spray outlet of the desuperheater.

[0018] As one of the achievable ways, the return point of the second condensate includes the condenser, the pipeline between the condensate pump and the low-temperature heater, and the deaerator;

[0019] According to the temperature and pressure of the second condensate, a return water point whose temperature and pressure are closest to those of the second condensate is selected, and the second condensate is sent into the nuclear power generation circulation loop.

[0020] As one possible implementation, the desuperheater is a mixing heat exchanger or a spray cooling facility.

[0021] The present invention also provides a nuclear power generation-steam supply method, using the above-mentioned nuclear power generation-steam supply system, comprising the following steps:

[0022] The steam generator absorbs the heat generated by the primary circuit of the nuclear power plant, heats the first condensate and the second condensate sent back by the nuclear power generation circulation circuit, generates the main steam of the secondary circuit of the nuclear power plant and sends it to the nuclear power generation circulation circuit and the nuclear steam supply circulation circuit;

[0023] The nuclear power generation cycle generates the first condensate after the main steam of the secondary circuit of the nuclear power plant sent to the steam generator is used for power generation, and the second condensate sent to the nuclear power steam supply cycle is sent back to the steam generator;

[0024] The nuclear energy steam supply circulation loop heats the industrial feed water with the main steam of the secondary circuit of the nuclear power plant sent by the steam generator to generate the second condensate and industrial steam; and sends them into the nuclear energy power generation circulation loop to generate industrial steam and send them to the industrial steam users;

[0025] According to the temperature and pressure of the second condensate, a return water point with a temperature and pressure closest to and lower than that of the second condensate is selected, and the second condensate is sent into a nuclear power generation circulation loop;

[0026] According to the industrial steam pressure required by the industrial steam user, the industrial steam pressure is adjusted to the industrial steam pressure required by the industrial steam user through the working fluid pump, and the industrial steam temperature is adjusted to the industrial steam temperature required by the industrial steam user through the desuperheater.

[0027] Beneficial technical effects of the present invention:

[0028] The nuclear power generation-steam supply system and method of the present invention adjusts the industrial steam pressure to the industrial steam pressure required by the industrial steam user through a working fluid pump, adjusts the industrial steam temperature to the industrial steam temperature required by the industrial steam user through a desuperheater, and controls the flow of desuperheating water entering the desuperheater through a regulating valve, thereby realizing precise regulation of industrial steam parameters; according to the temperature and pressure of the second condensate, a return water point with a temperature and pressure closest to the second condensate is selected, and the second condensate is sent into the nuclear power generation circulation loop, thereby realizing maximum recovery of the heat of the extracted condensate and improving the thermal efficiency of the nuclear steam supply; by reducing the complexity of the system and operating in a highly economical manner, it is possible to simultaneously adjust the industrial steam temperature and recover the heat of the extracted condensate, thereby providing industrial steam users with industrial steam of qualified parameters and improving the thermal efficiency of the nuclear steam supply. BRIEF DESCRIPTION OF THE DRAWINGS

[0029] Figure 1 It is a structural schematic diagram of an embodiment of the nuclear power generation-steam supply system of the present invention.

[0030] In the figure, 10, steam generator; 11, steam turbine; 12, generator; 13, condenser; 14, condensate pump; 15, low-temperature heater; 16, deaerator; 17, feed water pump; 18, high-temperature heater; 20, desalted water tank; 21, working fluid pump; 22, preheater; 23, industrial evaporator; 24, superheater; 25, desuperheater; 26, industrial steam user; 201, first regulating valve; 202, second regulating valve; 203, third regulating valve; 204, fourth regulating valve. DETAILED DESCRIPTION

[0031] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as those commonly understood by those skilled in the art to which this application belongs; the terms used herein in the specification of the application are only for the purpose of describing specific embodiments and are not intended to limit this application; the terms "including" and "having" and any variations thereof in the specification and claims of this application and the above-mentioned figure descriptions are intended to cover non-exclusive inclusions. In addition, the terms "first", "second", "third", "fourth", etc. are used for descriptive purposes only and are not to be understood as indicating or implying relative importance.

[0032] Reference to "embodiments" herein means that a particular feature, structure, or characteristic described in conjunction with the embodiments may be included in at least one embodiment of the present application. The appearance of the phrase in various locations in the specification does not necessarily refer to the same embodiment, nor is it an independent or alternative embodiment that is mutually exclusive with other embodiments. It is explicitly and implicitly understood by those skilled in the art that the embodiments described herein may be combined with other embodiments.

[0033] The technical solution of the present invention is clearly and completely described below in conjunction with the accompanying drawings and specific embodiments.

[0034] refer to Figure 1 , showing a schematic structural diagram of an embodiment of a nuclear power generation-steam supply system of the present invention, the nuclear power generation-steam supply system comprises a steam generator 10, a nuclear power generation cycle loop and a nuclear power steam supply cycle loop;

[0035] The steam generator 10 is configured to absorb the heat generated by the primary circuit of the nuclear power plant, heat the first condensate and the second condensate sent back by the nuclear power generation circulation circuit, generate the main steam of the secondary circuit of the nuclear power plant and send it into the nuclear power generation circulation circuit and the nuclear steam supply circulation circuit;

[0036] The nuclear power generation cycle is configured to generate first condensate from the secondary circuit main steam of the nuclear power plant fed into the steam generator 10 for power generation and to send it back to the steam generator 10; and to send second condensate fed into the nuclear power steam supply cycle back to the steam generator 10;

[0037] The nuclear energy steam supply circulation loop is configured to heat industrial feed water with the secondary loop main steam of the nuclear power plant fed by the steam generator 10 to generate secondary condensate and industrial steam;

[0038] A plurality of return water points of the second condensate are arranged in the nuclear power generation circulation loop; according to the temperature and pressure of the second condensate, a return water point with a temperature and pressure closest to and lower than that of the second condensate is selected, and the second condensate is sent into the nuclear power generation circulation loop;

[0039] A working fluid pump 21 and a desuperheater 25 are provided in the nuclear energy steam supply circulation loop. The working fluid pump 21 adjusts the industrial steam pressure, and the desuperheater 25 adjusts the industrial steam temperature.

[0040] In this embodiment, as one of the feasible ways, the nuclear power generation cycle loop includes a steam turbine 11, a generator 12, a condenser 13, a condensate pump 14, a low-temperature heater 15, a deaerator 16, a feed water pump 17 and a high-temperature heater 18 which are sequentially connected by pipelines, and the steam turbine 11 and the high-temperature heater 18 are respectively connected to the steam generator 10 by pipelines.

[0041] In this embodiment, as one of the achievable methods, the nuclear energy steam supply circulation loop includes a desalted water tank 20, a working fluid pump 21, a preheater 22, an industrial evaporator 23, a superheater 24, a desuperheater 25 and an industrial steam user 26; the preheater 22, the industrial evaporator 23 and the superheater 24 all include mutually isolated tube side paths and shell side paths;

[0042] The desalted water tank 20, the working fluid pump 21, the shell side path of the preheater 22, the shell side path of the industrial evaporator 23, the shell side path of the superheater 24, the desuperheater 25 and the industrial steam user 26 are connected by pipelines in sequence to form an industrial side loop; the tube side path of the preheater 22, the tube side path of the industrial evaporator 23 and the tube side path of the superheater 24 are connected by pipelines in sequence to form a heat source side loop;

[0043] The tube side path of the preheater 22 is connected to the pipeline of the steam generator 10, and the tube side path of the superheater 24 is respectively connected to the condenser 13, the deaerator 16, and the pipeline between the condensate pump 14 and the low-temperature heater 15; a second regulating valve 202 is provided on the pipeline connecting the tube side path of the superheater 24 to the condensate pump 14 and the pipeline between the low-temperature heater 15, a third regulating valve 203 is provided on the pipeline connecting the tube side path of the superheater 24 to the pipeline between the condensate pump 14 and the low-temperature heater 15, and a fourth regulating valve 204 is provided on the pipeline connecting the tube side path of the superheater 24 to the deaerator 16;

[0044] The outlet of the working fluid pump 21 is connected to the water spray outlet pipeline of the desuperheater 25 , and a first regulating valve 201 is provided on the pipeline connecting the outlet of the working fluid pump 21 and the water spray outlet of the desuperheater 25 .

[0045] In this embodiment, as one of the achievable ways, the return point of the second condensate includes the condenser 13, the pipeline between the condensate pump 14 and the low-temperature heater 15, and the deaerator 16;

[0046] According to the temperature and pressure of the second condensate, a return water point whose temperature and pressure are closest to those of the second condensate is selected, and the second condensate is sent into the nuclear power generation circulation loop.

[0047] By adjusting the return point of the second condensate, the heat of the extracted steam condensate can be recovered to the greatest extent possible, thereby improving the thermal efficiency of nuclear energy steam supply.

[0048] In this embodiment, as one of the feasible ways, the desuperheater 25 is a mixed heat exchanger or a spray cooling facility.

[0049] When the temperature of industrial steam needs to be lowered to a greater extent, the desuperheater 25 is a mixed heat exchanger; when the temperature of industrial steam needs to be lowered to a lesser extent, the desuperheater 25 is a spray cooling facility, so that the desuperheater 25 can handle a wider range of industrial steam parameter deviations from the operating conditions.

[0050] The working principle of the nuclear power generation-steam supply system of this embodiment is:

[0051] A part of the main steam of the secondary circuit of the nuclear power plant generated by the steam generator 10 is sent to the steam turbine 11 and the generator 12 to drive the steam turbine 11 and the generator 12 to generate electricity; the exhaust steam after power generation is sent to the condenser 13 to form the first condensate, and the first condensate is sent to the steam generator 10 after passing through the condensate pump 14, the low-temperature heater 15, the deaerator 16, the feed water pump 17 and the high-temperature heater 18.

[0052] Another part of the main steam of the nuclear power plant's secondary loop generated by the steam generator 10 is sent to the heat source side loop to heat the industrial feed water in the industrial side loop to form a second condensate; the second condensate is sent to the condenser 13, the deaerator 16 or the pipeline between the condensate pump 14 and the low-temperature heater 15 through the second regulating valve 202 or the third regulating valve 203 or the fourth regulating valve 204 according to its parameter quality, and then sent back to the steam generator 10 along the nuclear power generation circulation loop.

[0053] The industrial feed water in the industrial side loop is pressurized from the desalted water tank 20 by the working fluid pump 21, and passes through the shell side path of the preheater 22, the shell side path of the industrial evaporator 23, the shell side path of the superheater 24 and the desuperheater 25 in sequence to generate industrial steam; the working fluid pump 21 adjusts the industrial steam pressure to the industrial steam pressure required by the steam user, the desuperheater 25 adjusts the industrial steam temperature to the industrial steam temperature required by the industrial steam user, and the regulating valve 201 controls the flow of desuperheating water entering the desuperheater 25, thereby realizing precise regulation of industrial steam parameters.

[0054] This embodiment also provides a nuclear power generation-steam supply method, using the nuclear power generation-steam supply system of any embodiment, including the following steps:

[0055] The steam generator 10 absorbs the heat generated by the primary circuit of the nuclear power plant, heats the first condensate and the second condensate sent back by the nuclear power generation circulation circuit, generates the main steam of the secondary circuit of the nuclear power plant, and sends it into the nuclear power generation circulation circuit and the nuclear steam supply circulation circuit;

[0056] The nuclear power generation cycle generates first condensate water after the main steam of the secondary circuit of the nuclear power plant sent to the steam generator 10 is used for power generation, and the second condensate water sent to the nuclear power steam supply cycle is sent back to the steam generator 10;

[0057] The nuclear energy steam supply circulation loop heats the industrial feed water with the main steam of the nuclear power plant secondary circuit sent by the steam generator 10 to generate the second condensate and industrial steam; sends them into the nuclear energy power generation circulation loop to generate industrial steam and send them to the industrial steam user 26;

[0058] According to the temperature and pressure of the second condensate, a return water point with a temperature and pressure closest to and lower than that of the second condensate is selected, and the second condensate is sent into a nuclear power generation circulation loop;

[0059] According to the industrial steam pressure required by the industrial steam user, the industrial steam pressure is adjusted to the industrial steam pressure required by the industrial steam user through the working fluid pump 21, and the industrial steam temperature is adjusted to the industrial steam temperature required by the industrial steam user through the desuperheater 25.

[0060] The nuclear power generation-steam supply system and method provided in this embodiment can simultaneously adjust industrial steam parameters and recover the heat of extracted steam condensate, thereby providing industrial steam with qualified parameters to industrial steam users and improving the thermal efficiency of nuclear steam supply.

[0061] The above-mentioned embodiments only express several implementation methods of the present invention, and the description thereof is relatively specific and detailed, but it cannot be understood as limiting the scope of the patent of the present invention. It should be pointed out that, for ordinary technicians in this field, several variations and improvements can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention. Therefore, the protection scope of the patent of the present invention shall be subject to the attached claims.

Claims

1. A nuclear power generation-steam supply system, characterized in that: It comprises a steam generator (10), a nuclear power generation cycle loop and a nuclear steam supply cycle loop; The steam generator (10) is configured to absorb heat generated by the primary circuit of the nuclear power plant, heat the first condensate and the second condensate sent back by the nuclear power generation circulation circuit, generate the main steam of the secondary circuit of the nuclear power plant and send it into the nuclear power generation circulation circuit and the nuclear steam supply circulation circuit; The nuclear power generation circulation loop is configured to generate first condensate water after the main steam of the secondary circuit of the nuclear power plant sent into the steam generator (10) is used for power generation and is sent back to the steam generator (10); the second condensate water sent into the nuclear power steam supply circulation loop is sent back to the steam generator (10); The nuclear energy steam supply circulation loop is configured to heat industrial feed water with the secondary loop main steam of the nuclear power plant fed by the steam generator (10) to generate secondary condensate and industrial steam; A plurality of return water points of the second condensate are arranged in the nuclear power generation circulation loop; according to the temperature and pressure of the second condensate, a return water point with a temperature and pressure closest to and lower than that of the second condensate is selected, and the second condensate is sent into the nuclear power generation circulation loop; A working fluid pump (21) and a desuperheater (25) are provided in a nuclear energy steam supply circulation loop. The working fluid pump (21) adjusts the industrial steam pressure, and the desuperheater (25) adjusts the industrial steam temperature.

2. The nuclear power generation-steam supply system according to claim 1, characterized in that: The nuclear power generation cycle loop comprises a steam turbine (11), a generator (12), a condenser (13), a condensate pump (14), a low-temperature heater (15), a deaerator (16), a feed water pump (17) and a high-temperature heater (18) which are sequentially connected by pipelines. The steam turbine (11) and the high-temperature heater (18) are respectively connected to the steam generator (10) by pipelines.

3. The nuclear power generation-steam supply system according to claim 1, characterized in that: The nuclear energy steam supply circulation loop comprises a desalted water tank (20), a working fluid pump (21), a preheater (22), an industrial evaporator (23), a superheater (24), a desuperheater (25) and an industrial steam user (26); the preheater (22), the industrial evaporator (23) and the superheater (24) all comprise mutually isolated tube-side paths and shell-side paths; The desalted water tank (20), the working fluid pump (21), the shell side path of the preheater (22), the shell side path of the industrial evaporator (23), the shell side path of the superheater (24), the desuperheater (25) and the industrial steam user (26) are connected in sequence by pipelines to form an industrial side loop; the tube side path of the preheater (22), the tube side path of the industrial evaporator (23) and the tube side path of the superheater (24) are connected in sequence by pipelines to form a heat source side loop; The tube side path of the preheater (22) is connected to the pipeline of the steam generator (10), and the tube side path of the superheater (24) is respectively connected to the condenser (13), the deaerator (16), and the pipeline between the condensate pump (14) and the low-temperature heater (15); a second regulating valve (202) is provided on the pipeline connecting the tube side path of the superheater (24) and the condensate pump (14) and the low-temperature heater (15), a third regulating valve (203) is provided on the pipeline connecting the tube side path of the superheater (24) and the pipeline between the condensate pump (14) and the low-temperature heater (15), and a fourth regulating valve (204) is provided on the pipeline connecting the tube side path of the superheater (24) and the deaerator (16); The outlet of the working fluid pump (21) is connected to a pipe of a water spray outlet of the desuperheater (25), and a first regulating valve (201) is provided on the pipe connecting the outlet of the working fluid pump (21) and the water spray outlet of the desuperheater (25).

4. The nuclear power generation-steam supply system according to claim 3, characterized in that: The return point of the second condensate includes the condenser (13), the pipeline between the condensate pump (14) and the low-temperature heater (15), and the deaerator (16); According to the temperature and pressure of the second condensate, a return water point whose temperature and pressure are closest to those of the second condensate is selected, and the second condensate is sent into the nuclear power generation circulation loop.

5. The nuclear power generation-steam supply system according to claim 3, characterized in that: The desuperheater (25) is a mixed heat exchanger or a spray cooling facility.

6. A nuclear power generation-steam supply method, characterized in that: The nuclear power generation-steam supply system according to any one of claims 1 to 5 comprises the following steps: The steam generator (10) absorbs the heat generated by the primary circuit of the nuclear power plant, heats the first condensate and the second condensate sent back by the nuclear power generation circulation circuit, generates the main steam of the secondary circuit of the nuclear power plant and sends it into the nuclear power generation circulation circuit and the nuclear steam supply circulation circuit; The nuclear power generation circulation loop generates first condensed water after the main steam of the secondary circuit of the nuclear power plant sent to the steam generator (10) is used for power generation; and the second condensed water sent to the nuclear power steam supply circulation loop is sent back to the steam generator (10); The nuclear energy steam supply circulation loop heats industrial feed water with the secondary circuit main steam of the nuclear power plant sent by the steam generator (10), generating second condensate and industrial steam; and sending the steam to the nuclear energy power generation circulation loop to generate industrial steam, which is sent to the industrial steam user; According to the temperature and pressure of the second condensate, a return water point with a temperature and pressure closest to and lower than that of the second condensate is selected, and the second condensate is sent into a nuclear power generation circulation loop; According to the industrial steam pressure required by the industrial steam user, the industrial steam pressure is adjusted to the industrial steam pressure required by the industrial steam user through the working fluid pump (21), and the industrial steam temperature is adjusted to the industrial steam temperature required by the industrial steam user through the desuperheater (25).

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