CN213395266U - Blowdown and heat supply system of steam generator of nuclear power station - Google Patents

Blowdown and heat supply system of steam generator of nuclear power station Download PDF

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Publication number
CN213395266U
CN213395266U CN202020387611.7U CN202020387611U CN213395266U CN 213395266 U CN213395266 U CN 213395266U CN 202020387611 U CN202020387611 U CN 202020387611U CN 213395266 U CN213395266 U CN 213395266U
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blowdown
steam generator
heat
pipeline
heat supply
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CN202020387611.7U
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武心壮
况会英
夏栓
邱健
施伟
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Shanghai Nuclear Engineering Research and Design Institute Co Ltd
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Shanghai Nuclear Engineering Research and Design Institute Co Ltd
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02ATECHNOLOGIES FOR ADAPTATION TO CLIMATE CHANGE
    • Y02A30/00Adapting or protecting infrastructure or their operation
    • Y02A30/27Relating to heating, ventilation or air conditioning [HVAC] technologies
    • Y02A30/274Relating to heating, ventilation or air conditioning [HVAC] technologies using waste energy, e.g. from internal combustion engine

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Abstract

The utility model discloses a steam generator blowdown heating system of nuclear power station, including reactor pressure vessel and steam generator, be connected through reactor coolant pipeline between reactor pressure vessel and the steam generator, steam generator's both ends are equipped with main steam conduit and main water supply line respectively, steam generator is connected with blowdown heat supply interchanger through steam generator blowdown pipeline, be equipped with blowdown isolating valve on the steam generator blowdown pipeline, be connected with the main part and refrigerate the main part of heating on the blowdown heat supply interchanger respectively, the one end that reactor pressure vessel was kept away from to blowdown heat supply interchanger is equipped with the desalination main part. The utility model discloses from the comprehensive utilization angle of heat energy, be used for heat supply, refrigeration and increase the generated energy with steam generator's blowdown heat, reduced the energy consumption among the energy conversion process, improved nuclear power unit's economic nature.

Description

Blowdown and heat supply system of steam generator of nuclear power station
Technical Field
The utility model relates to a steam generator technical field especially relates to a steam generator blowdown heating system of nuclear power station.
Background
During the normal operation of the nuclear power station, the steam generator blowdown system controls the water chemistry property of the secondary side of the steam generator by discharging blowdown flow of the secondary side of the steam generator, and normally, the blowdown flow is recovered and reused after being cooled and purified. The nuclear power station factory and the outside of the factory inevitably have demands on heat supply, usually, high-temperature high-pressure steam is used for heating heat supply network water through a heat exchanger, and then the heat supply network water is supplied to each user through a heat supply network heat exchange station, and the high-temperature high-pressure steam is used as high-grade heat energy and is used for generating power to better reflect the value and the efficiency of energy utilization.
The existing blowdown and heat supply system is low in comprehensive utilization rate of heat energy, and therefore a blowdown and heat supply system of a steam generator of a nuclear power station is provided to solve the problems.
Disclosure of Invention
The utility model aims at solving the problem that the heat energy comprehensive utilization rate of the blowdown heating system existing in the prior art is lower, and providing a steam generator blowdown heating system of nuclear power station.
In order to achieve the above purpose, the utility model adopts the following technical scheme:
the utility model provides a steam generator blowdown heating system of nuclear power station, includes reactor pressure vessel and steam generator, be connected through reactor coolant pipeline between reactor pressure vessel and the steam generator, steam generator's both ends are equipped with main steam conduit and main water supply line respectively, steam generator is connected with blowdown heat supply interchanger through steam generator blowdown pipeline, be equipped with blowdown isolating valve on the steam generator blowdown pipeline, be connected with respectively on the blowdown heat supply interchanger and heat main part and refrigeration main part, the one end that reactor pressure vessel was kept away from to blowdown heat supply interchanger is equipped with the desalination main part.
Preferably, the heating main part includes the heat consumer, the both ends of heat consumer are equipped with heat consumer entry isolating valve and heat consumer export isolating valve respectively, the one end that heat consumer entry isolating valve and heat consumer export isolating valve carried on the back mutually is equipped with heat consumer entry pipeline and heat consumer export pipeline respectively, the one end that heat consumer entry pipeline and heat consumer export pipeline carried on the back mutually is equipped with heating system water main and heating system return water house steward respectively, and is equipped with heating system return water pump on the heating system return water house steward.
Preferably, the desalination main part includes the desalination device, the both ends of desalination device are equipped with desalination device outlet conduit and desalination device inlet pipe respectively, and are equipped with desalination device entry isolating valve on the desalination device inlet pipe.
Preferably, the refrigeration main body comprises a refrigerator, a refrigerator inlet pipeline and a refrigerator outlet pipeline are respectively arranged at two ends of the refrigerator, a refrigerator inlet isolation valve and a refrigerator outlet isolation valve are respectively arranged on the refrigerator inlet pipeline and the refrigerator outlet pipeline, and one ends of the refrigerator inlet pipeline and the refrigerator outlet pipeline, which are back to each other, are respectively communicated with the hot user inlet pipeline and the hot user outlet pipeline.
Preferably, the desalting device inlet pipeline is provided with a condensed water heater at one end far away from the desalting device, the condensed water heater is connected with the sewage supply heat exchanger through the condensed water heater inlet pipeline, the condensed water heater inlet pipeline is provided with a condensed water heater inlet isolating valve, and the condensed water heater is provided with condensed water.
The utility model discloses well beneficial effect as follows: the heat supply system is configured in the blow-off pipeline of the steam generator, blow-off heat of the steam generator is transferred to the heat supply system through the heat supply heater, partial heat is transferred to a heat user by the heat supply system in winter, partial heat is transferred to the refrigerator by the heat supply system in summer for cooling the user, blow-off flow heat after passing through the heat supply heater is transferred to the thermal system of the steam turbine through heating condensed water, the configuration starts from the comprehensive utilization angle of heat energy, the blow-off heat of the steam generator is used for supplying heat, refrigerating and increasing generated energy, the energy consumption in the energy conversion process is reduced, and the economical efficiency of the nuclear power unit is improved.
Drawings
Fig. 1 is a schematic structural view of a steam generator sewage heating system of a nuclear power station according to the present invention.
In the figure: 1 reactor pressure vessel, 2 reactor coolant pipeline, 3 steam generator, 4 main steam pipeline, 5 main water supply pipeline, 6 steam generator blowdown pipeline, 7 blowdown isolating valve, 8 blowdown heat exchanger, 9 condensed water heater inlet pipeline, 10 condensed water heater inlet isolating valve, 11 condensed water heater, 12 condensed water, 13 desalination device inlet pipeline, 14 desalination device inlet isolating valve, 15 desalination device, 16 water outlet pipelines of the desalting device, 17 water supply main pipes of the heating system, 18 inlet pipelines of the heat users, 19 inlet isolation valves of the heat users, 20 outlet isolation valves of the heat users, 21 outlet isolation valves of the heat users, 22 outlet pipelines of the heat users, 23 inlet pipelines of the refrigerating machine, 24 inlet isolation valves of the refrigerating machine, 25 refrigerating machine, 26 outlet isolation valves of the refrigerating machine, 27 outlet pipelines of the refrigerating machine, 28 water return pumps of the heating system and 29 water return main pipes of the heating system.
Detailed Description
The technical solutions in the embodiments of the present invention will be described clearly and completely with reference to the accompanying drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only some embodiments of the present invention, not all embodiments.
Referring to fig. 1, a blowdown and heat supply system of a steam generator of a nuclear power station comprises a reactor pressure vessel 1 and a steam generator 3, the reactor pressure vessel 1 is connected with the steam generator 3 through a reactor coolant pipeline 2, two ends of the steam generator 3 are respectively provided with a main steam pipeline 4 and a main water supply pipeline 5, the steam generator 3 is connected with a blowdown and heat supply exchanger 8 through a steam generator blowdown pipeline 6, the steam generator blowdown pipeline 6 is provided with a blowdown isolation valve 7, the blowdown and heat supply exchanger 8 is respectively connected with a heating body and a refrigerating body, one end of the blowdown and heat supply exchanger 8, which is far away from the reactor pressure vessel 1, is provided with a desalting body, during the unit power operation, heat of the reactor pressure vessel 1 is conveyed to the steam generator 3 through the reactor coolant pipeline 2, and feedwater enters the steam generator through the main water supply pipeline 5 to be heated into saturated steam, enters a steam turbine to do work and generate electricity through a main steam pipeline 4. The blowdown stream of the steam generator enters a blowdown heat exchanger 8 through a blowdown pipeline 6 of the steam generator and a blowdown isolation valve 7;
the heating main body comprises a heat user 20, a heat user inlet isolating valve 19 and a heat user outlet isolating valve 21 are respectively arranged at two ends of the heat user 20, a heat user inlet pipeline 18 and a heat user outlet pipeline 22 are respectively arranged at one end of the heat user inlet isolating valve 19 opposite to the heat user outlet isolating valve 21, a heat supply system water supply main pipe 17 and a heat supply system water return main pipe 29 are respectively arranged at one end of the heat user inlet pipeline 18 opposite to the heat user outlet pipeline 22, a heat supply system water return pump 28 is arranged on the heat supply system water return main pipe 29, during heating in winter, the hot user inlet isolation valve 19 and the hot user outlet isolation valve 21 are opened, the refrigerator inlet isolation valve 24 and the refrigerator outlet isolation valve 26 are closed, heat of blowdown flow is transmitted to the hot user 20 through the blowdown heat supply exchanger 8 and the hot user inlet pipeline 18, and return water returns to the blowdown heat supply exchanger 8 through the hot user outlet pipeline 22, the heat supply system water return pump 28 and the heat supply system water return header pipe 29 to complete circulation;
the desalting main body comprises a desalting device 15, a desalting device water outlet pipeline 16 and a desalting device inlet pipeline 13 are respectively arranged at two ends of the desalting device 15, a desalting device inlet isolation valve 14 is arranged on the desalting device inlet pipeline 13, a condensed water heater 11 is arranged at one end of the desalting device inlet pipeline 13 far away from the desalting device 15, the condensed water heater 11 is connected with a blowdown heat supply exchanger 8 through a condensed water heater inlet pipeline 9, a condensed water heater inlet isolation valve 10 is arranged on the condensed water heater inlet pipeline 9, condensed water 12 is arranged on the condensed water heater 11, after a blowdown flow passes through the blowdown heat supply exchanger 8, the blowdown flow enters the condensed water heater 11 through the condensed water heater inlet pipeline 9 and the condensed water heater inlet isolation valve 10, heat is transferred to the condensed water 12, heat is transferred to a turbine thermodynamic system, and the heat efficiency of the unit is improved, after passing through a condensate heater 11, the sewage enters a desalting device 15 through a desalting device inlet pipeline 13 and a desalting device inlet isolation valve 14, and water meeting the water quality requirement obtained after passing through the desalting device 15 is recycled through a desalting device outlet pipeline 16;
the refrigeration main body comprises a refrigerator 25, a refrigerator inlet pipeline 23 and a refrigerator outlet pipeline 27 are respectively arranged at two ends of the refrigerator 25, a refrigerator inlet isolation valve 24 and a refrigerator outlet isolation valve 26 are respectively arranged on the refrigerator inlet pipeline 23 and the refrigerator outlet pipeline 27, one end of the refrigerator inlet pipeline 23 opposite to the refrigerator outlet pipeline 27 is respectively communicated with a heat user inlet pipeline 18 and a heat user outlet pipeline 22, in summer, when cooling is carried out, the refrigerator inlet isolation valve 24 and the refrigerator outlet isolation valve 26 are opened, the hot user inlet isolation valve 19 and the hot user outlet isolation valve 21 are closed, heat of blowdown flow is transmitted to the refrigerator 25 through the blowdown heat supply exchanger 8 and the refrigerator inlet pipeline 23, and return water returns to the blowdown heat supply exchanger 8 through the refrigerator outlet pipeline 27, the heat supply system water return pump 28 and the heat supply system water return header 29 to complete circulation.
The utility model discloses in, during the unit power operation, reactor pressure vessel 1's heat passes through reactor coolant pipeline 2 and carries steam generator 3, and the feedwater gets into steam generator through main water supply pipe 5 and is heated into saturated steam, gets into the steam turbine through main steam pipe 4 and does work the electricity generation. The blowdown stream of the steam generator enters a blowdown heat exchanger 8 through a blowdown pipeline 6 of the steam generator and a blowdown isolation valve 7;
during heating in winter, the hot user inlet isolation valve 19 and the hot user outlet isolation valve 21 are opened, the refrigerator inlet isolation valve 24 and the refrigerator outlet isolation valve 26 are closed, heat of blowdown flow is transmitted to the hot user 20 through the blowdown heat supply exchanger 8 and the hot user inlet pipeline 18, and return water returns to the blowdown heat supply exchanger 8 through the hot user outlet pipeline 22, the heat supply system water return pump 28 and the heat supply system water return header pipe 29 to complete circulation;
in summer, when cooling is carried out, the refrigerator inlet isolating valve 24 and the refrigerator outlet isolating valve 26 are opened, the hot user inlet isolating valve 19 and the hot user outlet isolating valve 21 are closed, heat of blowdown flow is transmitted to the refrigerator 25 through the blowdown heat supply exchanger 8 and the refrigerator inlet pipeline 23, and return water returns to the blowdown heat supply exchanger 8 through the refrigerator outlet pipeline 27, the heat supply system water return pump 28 and the heat supply system water return header 29 to complete circulation;
the blowdown flows through the blowdown heat supply exchanger 8, then enters the condensate heater 11 through the condensate heater inlet pipeline 9 and the condensate heater inlet isolation valve 10, transfers heat to the condensate 12, realizes transferring heat to the turbine thermodynamic system, improves the unit thermal efficiency, enters the desalination device 15 through the desalination device inlet pipeline 13 and the desalination device inlet isolation valve 14 after passing through the condensate heater 11, and water meeting the water quality requirement obtained after passing through the desalination device 15 is recycled through the desalination device outlet pipeline 16.
The above, only be the concrete implementation of the preferred embodiment of the present invention, but the protection scope of the present invention is not limited thereto, and any person skilled in the art is in the technical scope of the present invention, according to the technical solution of the present invention and the utility model, the concept of which is equivalent to replace or change, should be covered within the protection scope of the present invention.

Claims (5)

1. The utility model provides a steam generator blowdown heating system of nuclear power station, includes reactor pressure vessel (1) and steam generator (3), its characterized in that, be connected through reactor coolant pipeline (2) between reactor pressure vessel (1) and steam generator (3), the both ends of steam generator (3) are equipped with main steam conduit (4) and main water supply pipe (5) respectively, steam generator (3) are connected with blowdown heat supply exchanger (8) through steam generator blowdown pipeline (6), be equipped with blowdown isolating valve (7) on steam generator blowdown pipeline (6), be connected with respectively on blowdown heat supply exchanger (8) and heat the main part with the refrigeration main part, the one end that reactor pressure vessel (1) was kept away from in blowdown heat supply exchanger (8) is equipped with the desalination main part.
2. The blowdown and heat supply system of the steam generator of the nuclear power station as claimed in claim 1, wherein the heating main body comprises a heat consumer (20), two ends of the heat consumer (20) are respectively provided with a heat consumer inlet isolation valve (19) and a heat consumer outlet isolation valve (21), one end of the heat consumer inlet isolation valve (19) opposite to the heat consumer outlet isolation valve (21) is respectively provided with a heat consumer inlet pipeline (18) and a heat consumer outlet pipeline (22), one end of the heat consumer inlet pipeline (18) opposite to the heat consumer outlet pipeline (22) is respectively provided with a heat supply system water supply header pipe (17) and a heat supply system water return header pipe (29), and the heat supply system water return header pipe (29) is provided with a heat supply system water return pump (28).
3. The blowdown and heat supply system of the steam generator of the nuclear power plant as claimed in claim 1, wherein the desalination main body comprises a desalination device (15), a desalination device water outlet pipe (16) and a desalination device inlet pipe (13) are respectively arranged at two ends of the desalination device (15), and a desalination device inlet isolation valve (14) is arranged on the desalination device inlet pipe (13).
4. The blowdown and heat supply system of the steam generator of the nuclear power plant as claimed in claim 2, wherein the refrigeration main body comprises a refrigerator (25), a refrigerator inlet pipeline (23) and a refrigerator outlet pipeline (27) are respectively arranged at two ends of the refrigerator (25), a refrigerator inlet isolation valve (24) and a refrigerator outlet isolation valve (26) are respectively arranged on the refrigerator inlet pipeline (23) and the refrigerator outlet pipeline (27), and one ends of the refrigerator inlet pipeline (23) opposite to the refrigerator outlet pipeline (27) are respectively communicated with the hot user inlet pipeline (18) and the hot user outlet pipeline (22).
5. A steam generator waste heat supply system for a nuclear power plant as claimed in claim 3, characterised in that the end of the demineralization apparatus inlet conduit (13) remote from the demineralization apparatus (15) is provided with a condensate heater (11), the condensate heater (11) is connected to the waste heat supply exchanger (8) by a condensate heater inlet conduit (9), the condensate heater inlet conduit (9) is provided with a condensate heater inlet isolation valve (10), and the condensate heater (11) is provided with condensate (12).
CN202020387611.7U 2020-03-24 2020-03-24 Blowdown and heat supply system of steam generator of nuclear power station Active CN213395266U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202020387611.7U CN213395266U (en) 2020-03-24 2020-03-24 Blowdown and heat supply system of steam generator of nuclear power station

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202020387611.7U CN213395266U (en) 2020-03-24 2020-03-24 Blowdown and heat supply system of steam generator of nuclear power station

Publications (1)

Publication Number Publication Date
CN213395266U true CN213395266U (en) 2021-06-08

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ID=76177090

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202020387611.7U Active CN213395266U (en) 2020-03-24 2020-03-24 Blowdown and heat supply system of steam generator of nuclear power station

Country Status (1)

Country Link
CN (1) CN213395266U (en)

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CP01 Change in the name or title of a patent holder

Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.

Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd.

CP01 Change in the name or title of a patent holder