CN110207523B - Multistage cooling system of nuclear power plant equipment cooling water - Google Patents
Multistage cooling system of nuclear power plant equipment cooling water Download PDFInfo
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- CN110207523B CN110207523B CN201910383791.3A CN201910383791A CN110207523B CN 110207523 B CN110207523 B CN 110207523B CN 201910383791 A CN201910383791 A CN 201910383791A CN 110207523 B CN110207523 B CN 110207523B
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
- F28D21/00—Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
- F28F27/00—Control arrangements or safety devices specially adapted for heat-exchange or heat-transfer apparatus
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
- F28D21/00—Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
- F28D2021/0019—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for
- F28D2021/0054—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for for nuclear applications
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The invention discloses a multistage cooling system for cooling water of nuclear power plant equipment, which comprises a multistage cooling unit and a high-temperature user unit connected with the multistage cooling unit in parallel, wherein a power unit is connected with the multistage cooling unit, the multistage cooling unit comprises at least one cooling series for cooling, each cooling system comprises a cooling pipeline, a plurality of heat exchangers connected on the cooling pipeline in series and a switch valve assembly for controlling the circulation or the cut-off of the cooling water flowing through each heat exchanger; the scheme has the beneficial technical effects that: the multi-stage cooling unit is arranged, so that the water supply temperature of the equipment cooling water system is gradually reduced, and the efficiency of a power plant is effectively improved by classifying and managing users; the self-selection characteristic of the multi-stage cooling unit enables the application of the whole system to be more flexible, any one working mode of multi-stage cooling can be selected for different sites of the nuclear power plant, and the economy of the power plant is integrally improved.
Description
Technical Field
The invention relates to the technical field of cooling equipment of nuclear power plants, in particular to a multistage cooling system for cooling water of equipment of a nuclear power plant.
Background
The primary function of the nuclear power plant equipment cooling water system is to cool various nuclear island heat exchangers, transfer the heat load through the heat exchanger cooled by the essential plant water system to the final heat sink seawater or air, forming a barrier between the nuclear island heat exchanger and the seawater or air, preventing uncontrolled release of radioactive fluid into the seawater or air.
The second generation and second generation pressurized water reactor nuclear power stations which are common at home and abroad all meet a criterion on the design of equipment cooling water systems: under the normal operation working condition, when the T7 temperature is adopted as the seawater inlet temperature of the heat exchanger, the equipment cooling water outlet temperature of the heat exchanger is lower than 35 ℃. However, for high temperature plants in tropical or subtropical climates in some south asian countries, the cold source temperature, i.e. the sea water or air temperature, can reach 33 ℃ or 34 ℃. Because the heat exchange temperature difference is only 1-2 ℃, the heat exchange area is very large, and great difficulty is brought to plant arrangement and field installation and maintenance of a nuclear power plant. In addition, the design of the original equipment cooling water system only has one-level cooling, and when the temperature of a cold source is low, the problem of overcooling of cooling water can be caused by adopting large heat exchange equipment. Since the equipment cooling water system and the important service water system have no grading cooling capability, the problems caused by only one-grade cooling are common in the cooling water systems of the equipment of the second-generation and second-generation pressurized water reactor nuclear power stations, as shown in fig. 1.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a multistage cooling system for cooling water of equipment of a nuclear power plant, which can meet the site condition of high temperature, optimizes the equipment and layout design, is flexible to use, can adopt any one working mode of multistage cooling for sites of different nuclear power plants, and integrally improves the economy of the power plants.
In order to realize the purpose, the technical scheme adopted by the invention is as follows:
the utility model provides a multistage cooling system of nuclear power plant equipment cooling water, this multistage cooling system of cooling water is including power pack, this multistage cooling system of cooling water still including multistage cooling unit and with the parallelly connected high temperature user unit of multistage cooling unit, power pack with multistage cooling unit links to each other, wherein multistage cooling unit is including at least one cooling series that is used for the cooling, each cooling system is including cooling line, series connection each are flowed through each to a plurality of heat exchangers on the cooling line and be used for controlling the cooling water the heat exchanger circulation or the switch valve subassembly that ends.
Furthermore, the cooling water multi-stage cooling system also comprises a low-temperature cooling user, wherein the low-temperature cooling user is connected with the multi-stage cooling unit in parallel.
Further, the switch valve assembly comprises isolation valves arranged on the front end and the rear end of each heat exchanger and bypass valves connected to the heat exchangers in parallel.
Further, the cooling system comprises a first heat exchanger and a second heat exchanger, the switch valve assembly comprises an upstream isolation valve, a middle isolation valve, a downstream isolation valve, a first heat exchanger bypass valve and a second heat exchanger bypass valve, wherein the upstream isolation valve is arranged at one upstream end of the first heat exchanger, the downstream isolation valve is arranged at one downstream end of the second heat exchanger, the middle isolation valve is arranged on a cooling pipeline between the first heat exchanger and the second heat exchanger, the first heat exchanger bypass valves are arranged at two ends of the first heat exchanger in parallel, and the second heat exchanger is arranged at two ends of the second heat exchanger in parallel.
Further, the power unit comprises at least two pipelines and at least two circulating cooling water pumps connected in series between the pipelines.
Furthermore, the high-temperature user unit comprises a ventilation heat exchanger, a chilled water heat exchanger, a spent pool heat exchanger, an installing and spraying heat exchanger, a waste heat deriving heat exchanger and a three-waste heat exchanger which are connected in parallel.
Furthermore, a thermometer, a flowmeter and two parallel pipelines are connected in series at one end of the low-temperature user unit, wherein a cold water heat exchanger and a pneumatic regulating valve are connected in series on one pipeline, and the other pneumatic regulating valve is connected on the other pipeline.
Furthermore, the low-temperature user unit comprises a plurality of sampling heat exchangers, a safety injection pump heat exchanger and other low-temperature heat exchangers which are connected in parallel.
Furthermore, one pneumatic control valve on the two pipelines feeds back the automatic control opening degree according to the thermometer, and the other pneumatic control valve on the two pipelines feeds back the automatic control opening degree according to the flow meter.
Further, a plurality of heat exchangers can be formed by heat exchangers with different power.
Compared with the prior art, the scheme has the beneficial technical effects that:
(1) The multi-stage cooling unit is configured, so that the water supply temperature of the equipment cooling water system is gradually reduced, and the efficiency of the power plant is effectively improved by classifying and managing users;
(2) The equipment and the arrangement design are optimized, so that the installation and the maintenance are more convenient;
(3) And the self-selection characteristic of the multi-stage cooling unit ensures that the whole system is more flexible to apply, and any one working mode of multi-stage cooling can be selected for different sites of the nuclear power plant, thereby integrally improving the economy of the power plant.
Drawings
Fig. 1 is a schematic view of a cooling water system of a conventional second generation or more nuclear power plant.
FIG. 2 is a schematic diagram of a nuclear power plant equipment cooling water system employing a multi-stage cooling unit according to the present invention.
Fig. 3 is a schematic diagram of a high temperature cooling subscriber unit of the present invention.
Fig. 4 is a schematic diagram of a cryogenically cooled consumer unit in accordance with the present invention.
FIG. 5 is a schematic diagram of a multi-stage cooling unit according to the present invention.
In the figure:
1-power unit, 2-multistage cooling unit, 3-high temperature user unit, 4-low temperature user unit, 11-circulating cooling water pump, 12-circulating cooling water pump, 21-first cooling series, 22-second cooling series, 23-multistage cooling unit, 201-upstream isolation valve, 202-first heat exchanger, 203-first heat exchanger bypass valve, 204-intermediate isolation valve, 205-second heat exchanger bypass valve, 206-second heat exchanger, 207-downstream isolation valve, 31-ventilation heat exchanger, 32-chilled water heat exchanger, 33-spent pool heat exchanger, 34-blowout heat exchanger, 35-waste heat export heat exchanger, 36-three waste heat exchanger, 41-pneumatic regulating valve, 42-pneumatic regulating valve, 43-cold water heat exchanger, 44-flow meter, 45-thermometer, 46-low temperature user unit, 47-sampling heat exchanger, 48-blowout pump heat exchanger, 49-blowout pump heat exchanger, 50-other low temperature heat exchanger.
Detailed Description
The invention is described in further detail below with reference to the drawings and the detailed description.
The scheme aims at the fact that a cooling water system and an important service water system of the existing nuclear power plant equipment do not have the capacity of graded cooling, and further provides the multistage cooling system for the cooling water of the nuclear power plant equipment.
Referring to the attached drawing, fig. 2 shows a multistage cooling system for cooling water of nuclear power plant equipment in the embodiment, which includes a power unit 1, a multistage cooling unit 2, and a high temperature user unit 3 and a low temperature user unit 4 connected in parallel with the multistage cooling unit 2, respectively. In practical use, the multi-stage cooling unit 2 and the low-temperature user unit 4 can independently exist, and the reservation condition of the low-temperature user unit 4 can be flexibly selected according to the practical use requirement of the multi-stage cooling unit. The power unit 1 is used for conveying cooling water in a system to the multistage cooling unit 2, heat exchange is carried out through the multistage cooling unit 2, the cooling water after heat exchange is input to the subsequent high-temperature user unit 3 or the subsequent low-temperature user unit 4 according to needs, and finally, under the action of the power unit 1, the cooling water circularly enters the multistage cooling unit 2, and cyclic utilization is achieved.
The power unit 1 is provided with at least two pipelines (i.e., points N1-N2 in fig. 2) and at least two circulating cooling water pumps 11, 12. The two circulating cooling water pumps 11 and 12 operate independently and have a standby use function. In practice, a user can select two or more circulating pumps according to the use requirement, and it can be understood that one circulating pump needs to be reserved for use in an emergency in order to ensure the maintenance requirement.
The multi-stage cooling unit 2 comprises a plurality of cooling series connected in parallel, each cooling system comprises a cooling pipeline, a plurality of heat exchangers connected in series on the cooling pipeline, and a switch valve assembly for controlling the flow or cut-off of cooling water flowing through each heat exchanger, and the switch valve assembly is a switch valve combined structure arranged on the heat exchangers to realize whether the cooling water in the cooling pipeline exchanges heat through the heat exchangers, namely, a user flexibly selects which heat exchangers in the cooling series are in working states according to specific cooling use requirements. Referring to fig. 2 and 5, the number of cooling series can be flexibly matched according to the specific situation of a user. Referring specifically to fig. 2, the multi-stage cooling unit 2 in the present embodiment includes two first cooling series 21 and two second cooling series 22 connected in parallel, and the first cooling series 21 and the second cooling series 22 have the same structure. The first cooling line 21 (the first cooling line 21 and the second cooling line 22 are the same, and for convenience of description, only the first cooling line 21 is described) in the present embodiment includes a cooling line (i.e., point N5 to point N6 in fig. 2) and an upstream isolation valve 201, a first heat exchanger 202, an intermediate isolation valve 204, a first heat exchanger bypass valve 203, a second heat exchanger 206, a second heat exchanger bypass valve 205, and a downstream isolation valve 207 connected in series to the cooling line, wherein the upstream isolation valve 201 is disposed at an upstream end of the first heat exchanger 202, the downstream isolation valve 207 is disposed at a downstream end of the second heat exchanger 206, the intermediate isolation valve 207 is disposed on the cooling line between the first heat exchanger 202 and the second heat exchanger 206, the first heat exchanger bypass valve 203 is disposed in parallel to a line (point N7 to point N9 in fig. 2) in which the first heat exchanger 202 and the intermediate isolation valve 204 are located, and the second heat exchanger bypass valve 205 is disposed in parallel to a line (point N8 to point N10 in fig. 2) in which the second heat exchanger 206 and the downstream isolation valve 207 are located.
During operation, when the temperature of a cold source is low, the first heat exchanger bypass valve 203 and the downstream isolation valve 204 are opened, the upstream isolation valve 201, the intermediate isolation valve 204 and the second heat exchanger bypass valve 205 are closed, so that the first heat exchanger 202 is bypassed, or the second heat exchanger bypass valve 205 and the upstream isolation valve 201 are opened, the first heat exchanger bypass valve 203, the intermediate isolation valve 204 and the downstream isolation valve 207 are closed, so that the second heat exchanger 206 is bypassed, so that one heat exchanger performs heat exchange operation; when the cold source temperature is high, the first and second heat exchanger bypass valves 203 and 206 are closed and the upstream, intermediate and downstream isolation valves 201, 204 and 207 are opened simultaneously so that the first and second heat exchangers 202 and 206 operate in series. It should be noted that, in actual operation, the power levels of the first heat exchanger 202 and the second heat exchanger 206 can be matched, that is, the heat exchanger with low bypass power is in normal operation, and when the temperature of the cold source is high, the two heat exchangers are connected in series for operation. It will be appreciated that in practice the number of heat exchangers can be flexibly adapted by the user as required, for example as shown in figure 5, i.e. a cooling train consisting of a plurality of heat exchangers in series.
Referring to fig. 3, the high temperature user unit 3 includes a plurality of high temperature users connected in parallel, that is, a ventilation heat exchanger 31, a chilled water heat exchanger 32, a spent pool heat exchanger 33, an injection heat exchanger 34, a waste heat deriving heat exchanger 35, and a three-waste heat exchanger 36, and the heat exchangers are connected in parallel to operate, and are connected in parallel with the multi-stage cooling unit 23 to realize a heat exchange function.
Referring to fig. 2 and 4 in combination, the low temperature consumer unit 4 is connected in series with two parallel lines (point N3-point N4 in fig. 2) and a temperature meter 45 and a flow meter 44 and parallel low temperature consumers. One of the two parallel pipelines is connected in series with a cold water heat exchanger 43 and a pneumatic control valve 41, and the other pipeline is connected with a pneumatic control valve 41. The pneumatic regulating valve 41 automatically controls the opening according to the feedback of the thermometer, so as to ensure that the temperature of the mixed cold and hot fluid at the outlet meets the requirement of a low-temperature user, and is generally not higher than 30 ℃; the pneumatic control valve 42 automatically controls the opening according to the feedback of the flow meter, and ensures that the total flow is constant.
The low-temperature user unit 46 comprises a sampling heat exchanger 47, a safety injection pump heat exchanger 48, a safety injection pump heat exchanger 49 and other low-temperature heat exchangers 50, the heat exchangers run in parallel, namely the heat exchangers are connected with the multistage cooling unit 23 in parallel, and the heat exchange function is realized.
In conclusion, the cooling water multistage cooling system in the scheme can meet the plant site conditions of high temperature, optimizes equipment and layout design, is flexible to use, can adopt any working mode of multistage cooling for plant sites of different nuclear power plants, and integrally improves the economical efficiency of the power plants.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations.
Claims (4)
1. The utility model provides a multistage cooling system of nuclear power plant equipment cooling water, this multistage cooling system of cooling water is including power pack, its characterized in that: the cooling water multistage cooling system also comprises a multistage cooling unit, a high-temperature user unit and a low-temperature user unit which are connected with the multistage cooling unit in parallel, wherein the power unit is connected with the multistage cooling unit, the multistage cooling unit comprises at least one cooling series used for cooling, each cooling series comprises a cooling pipeline, a plurality of heat exchangers connected on the cooling pipeline in series and a switch valve assembly used for controlling the cooling water to flow through each heat exchanger or be stopped, the switch valve assembly comprises isolation valves arranged at the front end and the rear end of each heat exchanger and bypass valves connected on the heat exchangers in parallel, the cooling series comprises a first heat exchanger and a second heat exchanger, the switch valve assembly comprises an upstream isolation valve, a middle isolation valve, a downstream isolation valve, a first heat exchanger bypass valve and a second heat exchanger bypass valve, wherein the upstream isolation valve is arranged at one end of the upstream of the first heat exchanger, the downstream isolation valve is arranged at one end of the downstream of the second heat exchanger, the middle isolation valve is arranged on a cooling pipeline between the first heat exchanger and the second heat exchanger, the first heat exchanger bypass valve is arranged on a pipeline where the first heat exchanger and the middle isolation valve are located in parallel, the second heat exchanger bypass valve is arranged on a pipeline where the second heat exchanger and the downstream isolation valve are located in parallel, and the high-temperature user unit comprises a ventilation heat exchanger, a chilled water heat exchanger, a spent pool heat exchanger, a blowout heat exchanger, a waste heat deriving heat exchanger and a three-waste heat exchanger which are connected in parallel; the low-temperature user unit comprises a plurality of sampling heat exchangers, a safety injection pump heat exchanger and other low-temperature heat exchangers which are connected in parallel.
2. The multi-stage cooling system for cooling water of nuclear power plant equipment according to claim 1, characterized in that: the power unit comprises at least two pipelines and at least two circulating cooling water pumps connected in series between the pipelines.
3. The multi-stage cooling system for cooling water of nuclear power plant equipment according to claim 2, characterized in that: one end of the low-temperature user unit is connected with a thermometer, a flowmeter and two parallel pipelines in series, wherein one pipeline is connected with a cold water heat exchanger and a pneumatic regulating valve in series, and the other pipeline is connected with the other pneumatic regulating valve in series.
4. The multi-stage cooling system for cooling water of nuclear power plant equipment according to claim 3, characterized in that: and the pneumatic regulating valve connected to one pipeline feeds back the opening automatically according to the thermometer, and the other pneumatic regulating valve connected to the other pipeline feeds back the opening automatically according to the flowmeter.
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| CN201910383791.3A CN110207523B (en) | 2019-05-08 | 2019-05-08 | Multistage cooling system of nuclear power plant equipment cooling water |
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| CN201910383791.3A CN110207523B (en) | 2019-05-08 | 2019-05-08 | Multistage cooling system of nuclear power plant equipment cooling water |
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| CN110207523B true CN110207523B (en) | 2022-12-09 |
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| CN111578570A (en) * | 2020-05-13 | 2020-08-25 | 西安交通大学 | System for acquiring large supercooling degree of liquid oxygen by utilizing liquid hydrogen cooling capacity |
| CN112078773A (en) * | 2020-08-04 | 2020-12-15 | 沪东中华造船(集团)有限公司 | Series-parallel integrated marine cooling system and control method thereof |
| CN113139330B (en) * | 2021-03-29 | 2021-11-30 | 中国核电工程有限公司 | Nuclear power plant cold chain system configuration method based on improved genetic algorithm |
| CN113409968A (en) * | 2021-05-18 | 2021-09-17 | 中国核电工程有限公司 | Refrigerating system used under nuclear power plant heat sink loss working condition |
| CN113421662B (en) * | 2021-06-18 | 2022-04-15 | 中国核动力研究设计院 | Natural circulation cooling method under failure of liquid level indication of pressure vessel of nuclear power plant |
| CN115331849A (en) * | 2022-09-14 | 2022-11-11 | 上海核工程研究设计院有限公司 | Passive residual heat removal system and method for nuclear reactor |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN201809467U (en) * | 2010-07-27 | 2011-04-27 | 郑松秋 | Tank solution cooling system used in aluminum fabrication |
| CN203552714U (en) * | 2013-11-22 | 2014-04-16 | 中广核工程有限公司 | Nuclear power plant device cooling water system |
| CN103871530B (en) * | 2014-03-19 | 2017-04-19 | 中广核工程有限公司 | Series dividing and cooling framework of users of nuclear power plant equipment cooling water system |
| CN104990337B (en) * | 2015-06-19 | 2017-07-07 | 青岛华控能源科技有限公司 | Recirculating cooling water system and its method |
| DE102017210271A1 (en) * | 2016-11-29 | 2018-05-30 | Mahle International Gmbh | Heat exchanger, in particular exhaust gas heat exchanger, for a motor vehicle |
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