Nuclear cogeneration heat supply system

Abstract

The present application relates to a kind of nuclear energy cogeneration heat supply system, comprising: at least two nuclear energy heat supply device, each nuclear energy heat supply device includes intercommunication steam supply system and start separation system;Steam supply system provides steam, start separation system includes start separator, water removal system, steam interface, steam outlet and water removal interface;Start separator, water removal system intercommunication, steam interface connects steam supply system and start separator, steam outlet connects start separator and water removal system, water removal interface connects water removal system;And distribution system, steam outlet is connected to distribution system and load, water removal interface is connected to distribution system, and distribution system is connected to load, load is connected to steam supply system and water removal system, water removal system is connected to steam supply system.The steam of multiple nuclear energy heat supply device can be after gathering to the external heat supply load again supply, let heat supply be more uniform, and heat supply mode is various.

Description

TECHNICAL FIELD

[0001] The present application relates to the field of nuclear power, more particularly, to a heat supply system for nuclear cogeneration. BACKGROUND

[0002] The once-through steam generator (OTSG) has been widely used in nuclear power plants at home and abroad due to its small size, good maneuverability, and high thermal efficiency. During the start-stop process of the OTSG, there is strong flow instability and wall temperature fluctuation, accompanied by dry-wet alternating phenomenon. Therefore, a reactor start-stop auxiliary system is provided to match the OTSG, which plays a very important role in the heat start process of the reactor and is an indispensable system.

[0003] The nuclear power industry in China widely adopts unitized reactor-turbine configuration, that is, a one-to-one relationship between the reactor and the turbine and forms a unit. With the development of nuclear energy at home and abroad, the demand for nuclear reactors for various application scenarios of heat and power cogeneration is increasing. In addition to pure power generation applications, nuclear reactors can also supply steam for industrial heating, residential heating, refrigeration, seawater desalination, and other extended applications.

[0004] Different application scenarios have different load types and sizes. One reactor or several reactors can supply steam for both turbine power generation and industrial heating, residential heating, refrigeration, seawater desalination, etc. The turbine can be single or multiple (two or more). The steam supply can be at one pressure or at several pressures simultaneously. New steam can be used for heating, or turbine extraction steam can be used for heating. Therefore, in the case of heat and power cogeneration, it is difficult to achieve a one-to-one correspondence between the reactor and the load. Instead, multiple reactors or one reactor can supply steam for multiple loads. The types of loads include pure power generation turbines, extraction heating turbines, heat exchangers, etc. The types of loads carried by the reactor can be one or a combination of some or all of these types. The number of loads carried by the reactor can be one or multiple. For ease of description, we refer to the combination of reactors, turbines, and heat exchangers as "multiple reactor-turbine-heat cogeneration".

[0005] In the case of multiple reactor-turbine-heat cogeneration, how to meet the requirements of reactor-turbine heat start-stop and mutual connection and coordination is a technical problem that the current reactor start-stop auxiliary system cannot solve.

[0006] In the nuclear energy industry, in addition to unitized nuclear power units, the only high-temperature gas-cooled reactor that has been put into operation and partially meets the multiple reactor-turbine-heat characteristics is the high-temperature gas-cooled reactor. This reactor type uses two reactors with one turbine for power generation, solving the problem of setting up a start-stop reactor auxiliary system for two high-temperature gas-cooled reactors with one turbine.

[0007] The high-temperature gas cooled reactor two-pile one-machine is only a very special scene of multiple piles, multiple machines and multiple heat, and does not have universality and cannot solve the connection problem and mutual coordination problem of various application scenes of multiple piles, multiple machines and multiple heat. SUMMARY

[0008] The technical problem to be solved by the present application is to provide a nuclear energy cogeneration heat supply system to solve the above-mentioned defects of the prior art.

[0009] The technical scheme adopted by the present application to solve the technical problem is: a nuclear energy cogeneration heat supply system is constructed, comprising:

[0010] At least two nuclear energy heat supply devices, each of which comprises a steam supply system and a start-up separation system in communication with each other; the steam supply system provides steam, and the start-up separation system comprises a start-up separator, a drain system, a steam interface, a steam outlet, and a drain interface; the start-up separator and the drain system are in communication with each other, the steam interface is connected to the steam supply system and the start-up separator, the steam outlet is connected to the start-up separator and the drain system, and the drain interface is connected to the drain system; and

[0011] A distribution system, the steam outlet is connected to the distribution system and a load, the drain interface is connected to the distribution system, and the distribution system is connected to the load, the load is connected to the steam supply system and the drain system, and the drain system is connected to the steam supply system.

[0012] In some embodiments, the start-up separator is provided with a first interface connected to the steam outlet, and the drain system is provided with a third interface connected to the steam outlet.

[0013] In some embodiments, the distribution system comprises a drain main pipe and a steam distribution unit.

[0014] The drain interface is connected to the drain main pipe, the steam outlet is connected to the steam distribution unit, and the drain main pipe and the steam distribution unit are respectively connected to the heat supply load.

[0015] In some embodiments, the steam distribution unit comprises a bypass main pipe and an insulation steam main pipe.

[0016] The steam outlet is connected to a plurality of first branches, the first branches are respectively connected to the bypass main pipe and the insulation steam main pipe, and the bypass main pipe and the insulation steam main pipe are respectively connected to the load.

[0017] In some embodiments, the load includes a main steam header, a load unit, a main feedwater header, the steam outlet is connected to the bypass header through a branch, the bypass header is connected to the main steam header, the main steam header is connected to the load unit, the load unit is connected to the main feedwater header, and the main feedwater header is connected to the nuclear heat supply device.

[0018] In some embodiments, the load includes a steam turbine, a condenser, a heat exchanger, and a condensate feedwater system, each load unit includes at least one of a steam turbine, a condenser, a heat exchanger, and a condensate feedwater system, and each load unit includes at least two steam inlets, the insulation steam header is connected to the condensate feedwater system, and the drain header is connected to the condenser.

[0019] In some embodiments, the main feedwater header is connected to the nuclear heat supply device through a feedwater branch, the feedwater branch includes a fourth branch connected to the steam supply system and a fifth branch connected to the startup separator system.

[0020] In some embodiments, the steam supply system includes at least two evaporators and a steam header, the evaporators are connected in parallel and connected to the steam header respectively;

[0021] The startup separator is provided with a second interface connected to an insulation steam source and a steam header of the steam supply system to deliver steam into the startup separator.

[0022] In some embodiments, the steam header is connected with a second branch, the second branch is connected to the main steam header in parallel with a first branch of the steam outlet, and the second branch is provided with a steam control valve.

[0023] In some embodiments, the fourth branch is provided with a feedwater header connected to each evaporator of the steam supply system respectively;

[0024] The third interface is provided with a drain circulating pump, the drain system is provided with a fourth interface, the fourth interface is provided with a drain regulating valve, the drain circulating pump and the drain regulating valve are connected to each evaporator respectively in parallel;

[0025] The fifth branch is connected to the third interface.

[0026] The heating system of nuclear cogeneration according to the present invention has the following beneficial effects: the steam from multiple nuclear heating devices in the heating system of the present invention can be collected and then supplied to the external heating load, making the heat supply more uniform. The configuration of the nuclear heating devices can be the same or different. They can directly discharge steam to the load for heating, or the distribution system can discharge steam to the load for heating. The heating methods are diverse, which is conducive to integrating different nuclear heating devices for heating, facilitating coordination and improving heating efficiency. Attached Figure Description

[0027] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings:

[0028] Figure 1 This is a schematic diagram illustrating the connection between the heating system and the load in a nuclear cogeneration system according to an embodiment of the present invention.

[0029] Figure 2 yes Figure 1 Schematic diagram of the steam supply system;

[0030] Figure 3 yes Figure 1 A schematic diagram of the principle of the start-up separation system;

[0031] Figure 4 yes Figure 1 The first load unit arranged from top to bottom for medium loads;

[0032] Figure 5 yes Figure 1 The second load unit arranged from top to bottom for medium loads;

[0033] Figure 6 yes Figure 1 The third load unit arranged from top to bottom for medium loads;

[0034] Figure 7 yes Figure 1 The fourth load unit arranged from top to bottom for medium loads. Detailed Implementation

[0035] To provide a clearer understanding of the technical features, objectives, and effects of the present invention, specific embodiments of the present invention will now be described in detail with reference to the accompanying drawings.

[0036] like Figures 1 to 3 As shown, in a preferred embodiment of the present invention, the heating system of nuclear cogeneration includes two nuclear heating devices 1 and a distribution system 2. The number of nuclear heating devices 1 may also be more than two.

[0037] Each nuclear energy heat supply device 1 comprises a steam supply system 11 and a start-up separation system 12 which are communicated with each other; the steam supply system 11 can supply steam from the reactor 111 outward, preferably, in the embodiment, the steam supply system 11 comprises the reactor 111 and a steam header 112, the reactor 111 comprises two evaporators 1111, it can be understood that the number of the evaporators 1111 of the reactor 111 can also be more than two, the evaporators 1111 are connected in parallel and are connected to the steam header 112 respectively, so that the steam and the steam-water mixture of the evaporators 1111 are collected and mixed in the steam header 112 and then are supplied outward, so that the heat supply is more uniform.

[0038] Further, the start-up separation system 12 comprises a start-up separator 121, a drain system 122, a steam interface 123, a steam outlet 124 and a drain interface 125. Specifically, the start-up separator 121 and the drain system 122 are communicated with each other, the drain separated by the start-up separator 121 can directly enter the drain system 122, the steam interface 123 communicates the steam supply system 11 and the start-up separator 121, so that the medium at the outlet of the evaporator 1111 enters the start-up separator 121. The steam outlet 124 communicates the start-up separator 121 and the drain system 122, so that the steam entering the start-up separation system 12 is discharged outward through the steam outlet 124, and the drain interface 125 communicates the drain system 122, so that the steam in the drain system 122 is discharged outward.

[0039] In the embodiment, the steam outlet 124 is connected to the distribution system 2 and the load 3, the drain interface 125 is connected to the distribution system 2, and the distribution system 2 is communicated to the load 3, the load 3 is communicated to the steam supply system 11 and the drain system 122, and the drain system 122 is communicated to the steam supply system 11.

[0040] The steam of the plurality of nuclear energy heat supply devices 1 of the nuclear energy cogeneration heat supply system can be collected and then supplied to the load 3 outward, so that the heat supply is more uniform, the nuclear energy heat supply devices 1 can be the same or different, can directly discharge steam to the load 3 for heat supply, or can discharge steam to the load 3 for heat supply through the distribution system 2, so that the heat supply mode is various, which is beneficial to integrate different nuclear energy heat supply devices 1 for heat supply, and is convenient for coordinating and improving the heat supply efficiency.

[0041] Preferably, the steam outlet 124 is connected with a plurality of first branches 126, each first branch 126 can be connected to the distribution system 2 and the load 3 and is discharged according to the discharge demand, so as to meet different heat supply demands.

[0042] In the embodiment, the start-up separator 121 is provided with a first interface 1211 and a second interface 1212, the first interface 1211 is connected to the steam outlet 124, in addition, the drain system 122 is provided with a third interface 1221, the third interface 1221 is connected to the steam outlet 124, so that the steam in the start-up separator 121 and the steam in the drain system 122 can be discharged to the outside through the steam outlet 124. Further, the second interface 1212 can be connected to the heat preservation steam source 4 and the steam header 112 of the steam supply system 11 in two ways respectively, so as to transport steam into the start-up separator 121 and the drain system 122.

[0043] The steam header 112 is connected with a second branch 1121 and a third branch 1122, the second branch 1121 is connected to the main steam header 31 of the load 3 in parallel with a first branch 126 of the steam outlet 124, and the second branch 1121 is provided with a steam control valve 1123, which can control the on-off and flow of the second branch 1121. The third branch 1122 is connected to the second interface 1212, and provides steam to the start-up separation system 12 and the drain system 122, which is the path of the steam and the steam-water mixture discharged from the nuclear steam supply system 11 to the start-up separator 121 system.

[0044] In some embodiments, the distribution system 2 includes a drain header 21 and a steam distribution unit 22, the drain interface 125 is connected to the drain header 21, the steam outlet 124 is connected to the steam distribution unit 22, and the drain header 21 and the steam distribution unit 22 are respectively connected to the load 3. The drain in the drain header 21 is supplied to the steam side of the condenser 322 of the load 3, and the steam in the steam distribution unit 22 can be discharged to the steam turbine 321, the heat exchanger 323, the feedwater system 324 and other devices of the load 3.

[0045] Specifically, in the embodiment, the steam distribution unit 22 includes a bypass header 221 and a heat preservation steam header 222, and each first branch 126 is connected to the bypass header 221 and the heat preservation steam header 222, respectively. The bypass header 221 and the heat preservation steam header 222 are connected to the load 3. Of course, the steam distribution unit 22 can also include more than two distribution pipes.

[0046] Further, as shown in FIG. 1, Figure 1 As shown in FIG. 1, the load 3 includes a main steam header 31, a load unit 32, and a main feedwater header 33, the steam outlet 124 is connected to the bypass header 221 through the first branch 126, the bypass header 221 is connected to the main steam header 31, the main steam header 31 is connected to the load unit 32, the load unit 32 is connected to the main feedwater header 33, and the main feedwater header 33 is connected to the nuclear energy heating device 1, so that the steam is returned to the nuclear energy heating device 1 after being heated after being cooled.

[0047] Preferably, load 3 includes a steam turbine 321, a condenser 322, a heat exchanger 323, and a condensate feedwater system 324. Each load unit 32 includes at least one of the following: steam turbine 321, condenser 322, heat exchanger 323, and condensate feedwater system 324. In this embodiment, each load unit 32 can be a combination of the above components, such as... Figures 4 to 7 As shown, in order are Figure 1 The four load units 32 are arranged from top to bottom. Furthermore, each load unit 32 includes at least two steam inlets 325, an insulated steam header 222 connected to a condensate feedwater system 324, a deaerator in the condensate feedwater system 324, and a drain header 21 connected to the condenser 322.

[0048] In combination Figures 1 to 3 As shown, in some embodiments, the main water supply header 33 is connected to the nuclear heating device 1 via water supply branches 331. The water supply branches 331 include a fourth branch 3311 connected to the steam supply system 11 and a fifth branch 3312 connected to the start-up separation system 12.

[0049] The fourth branch 3311 is the path for supplying water to the steam supply system 11. Preferably, the fourth branch 3311 is equipped with a water pump 3313 and a water header 3314. The water pump 3313 delivers water to the water header 3314. The water header 3314 is connected to each evaporator 1111 of the steam supply system 11, allowing the water returning to the water header 3314 to flow evenly to each evaporator 1111. This path from the water supply to the evaporators 1111 is the path for the nuclear steam supply system 11 after the separator 121 is started and the system goes offline.

[0050] The third interface 1221 is equipped with a condensate circulation pump 1222. The condensate system 122 is equipped with a fourth interface 1223. The fourth interface 1223 is equipped with a condensate regulating valve 1224. The condensate circulation pump 1222 and the condensate regulating valve 1224 are connected in parallel and then merged into a single pipe. They are then connected to each evaporator 1111 through a sixth branch 1225, so that the condensate in the condensate system 122 can also flow evenly to each evaporator 1111. This is the circulation path of the start-up separator 121 medium inside the nuclear steam nuclear energy heating device 1.

[0051] The fifth branch 3312 is connected to the third interface 1221, and the discharge to the third interface 1221 can be controlled by a valve. This is the path for the water supply to start the separator 121 system.

[0052] Preferably, control valves and regulating valves can be installed on the pipeline to control the on / off state of each branch. In addition, the working principles between different nuclear heating devices 1 and distribution systems 2 are the same, and will not be described in detail here.

[0053] The present application solves the problem of connecting pipelines in a multi-heap multi-machine multi-heat cogeneration situation, and provides a start-stop heap control method based on a general connection mode.

[0054] The present application is applicable to the case where multiple steam turbines 321 and multiple load units 32 work together, and all steam turbines 321 can be designed completely the same, or can be completely different in type, capacity, parameters and thermal system configuration, such as Figure 1 、 5 , as shown in 6, the third load unit 32 can be steam extraction from the steam turbine 321 of the second load unit 32 for heating, or can be directly connected to the load unit 32 by the main pipe of the distribution system 2 for steam for another user's heating.

[0055] It can be understood that the above technical features can be used in any combination without limitation.

[0056] The above is only an embodiment of the present application, and does not limit the patent scope of the present application, and any equivalent structure or equivalent process transformation using the content of the present application specification and drawings, or direct or indirect application in other related technical fields, are also included in the patent protection scope of the present application.

Claims

1. A heating system for nuclear cogeneration, characterized in that, include: At least two nuclear heating units (1), each of the nuclear heating units (1) including an interconnected steam supply system (11) and a start-up separation system (12); the steam supply system (11) provides steam, and the start-up separation system (12) includes a start-up separator (121), a condensate drain system (122), a steam inlet (123), a steam outlet (124), and a condensate drain outlet (125); the start-up separator (121) and the condensate drain system (122) are interconnected, the steam inlet (123) connects the steam supply system (11) and the start-up separator (121), the steam outlet (124) connects the start-up separator (121) and the condensate drain system (122), and the condensate drain outlet (125) connects the condensate drain system (122); and Distribution system (2), the steam outlet (124) is connected to the distribution system (2) and the load (3), the drain port (125) is connected to the distribution system (2), and the distribution system (2) is connected to the load (3), the load (3) is connected to the steam supply system (11) and the drain system (122), the drain system (122) is connected to the steam supply system (11); The distribution system (2) includes a drain header (21) and a steam distribution unit (22); the drain port (125) is connected to the drain header (21), the steam outlet (124) is connected to the steam distribution unit (22), and the drain header (21) and the steam distribution unit (22) are respectively connected to the load (3); The steam distribution unit (22) includes a bypass header (221) and an insulated steam header (222); the steam outlet (124) is connected to a plurality of first branches (126), the first branches (126) being connected to the bypass header (221) and the insulated steam header (222) respectively, and the bypass header (221) and the insulated steam header (222) being connected to the load (3) respectively; The load (3) includes a main steam header (31), a load unit (32), and a main feedwater header (33). The steam outlet (124) is connected to the bypass header (221) via a branch. The bypass header (221) is connected to the main steam header (31). The main steam header (31) is connected to the load unit (32). The load unit (32) is connected to the main feedwater header (33). The main feedwater header (33) is connected to the nuclear heating device (1). The steam supply system (11) includes at least two evaporators (1111) and a steam header (112). The evaporators (1111) are arranged in parallel and connected to the steam header (112) respectively. The start-up separator (121) is provided with a second interface (1212), which is connected to the heat-insulating steam source (4) and the steam header (112) of the steam supply system (11) to supply steam into the start-up separator (121). The steam header (112) is connected to a second branch (1121), which is connected in parallel with a first branch (126) of the steam outlet (124) and then connected to the main steam header (31). A steam control valve (1123) is provided on the second branch (1121).

2. The heating system for nuclear cogeneration according to claim 1, characterized in that, The start-up separator (121) is provided with a first interface (1211) connected to the steam outlet (124), and the condensate system (122) is provided with a third interface (1221) connected to the steam outlet (124).

3. The heating system for nuclear cogeneration according to claim 1, characterized in that, The load (3) includes a steam turbine (321), a condenser (322), a heat exchanger (323), and a condensate feedwater system (324). Each load unit (32) includes a steam turbine (321), a condenser (322), a heat exchanger (323), and a condensate feedwater system (324). Each load unit (32) includes at least two steam inlets (325). The insulated steam header (222) is connected to the condensate feedwater system (324), and the drain header (21) is connected to the condenser (322).

4. The heating system for nuclear cogeneration according to claim 2, characterized in that, The main water supply header (33) is connected to the nuclear heating device (1) via water supply branches (331). The water supply branches (331) include a fourth branch (3311) connected to the steam supply system (11) and a fifth branch (3312) connected to the start-up separation system (12).

5. The heating system for nuclear cogeneration according to claim 4, characterized in that, The fourth branch (3311) is provided with a water supply manifold (3314), which is connected to each of the evaporators (1111) of the steam supply system (11). The third interface (1221) is provided with a hydrophobic circulation pump (1222), the hydrophobic system (122) is provided with a fourth interface (1223), the fourth interface (1223) is provided with a hydrophobic regulating valve (1224), the hydrophobic circulation pump (1222) and the hydrophobic regulating valve (1224) are connected in parallel and then connected to each of the evaporators (1111). The fifth branch (3312) is connected to the third interface (1221).

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