CN113113161A - Nuclear energy steam supply system - Google Patents
Nuclear energy steam supply system Download PDFInfo
- Publication number
- CN113113161A CN113113161A CN202110368638.0A CN202110368638A CN113113161A CN 113113161 A CN113113161 A CN 113113161A CN 202110368638 A CN202110368638 A CN 202110368638A CN 113113161 A CN113113161 A CN 113113161A
- Authority
- CN
- China
- Prior art keywords
- heat
- pipeline
- steam
- supply
- nuclear energy
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- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
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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
- Y02E30/30—Nuclear fission reactors
Abstract
The invention relates to the field of nuclear power heat supply, in particular to a nuclear energy steam supply system, which comprises: nuclear reactor coolant piping; the nuclear reactor coolant flows out of the nuclear reactor, enters the heat supply side of the heat exchange device through a pipeline and then returns to the nuclear reactor through the pipeline; the system comprises a water supply pipe, a heat exchange device, a low-temperature steam pipe, a heating device, a power generation device and a water supply pipe, wherein the water supply pipe is connected with the heat exchange device and the heat exchange device through a pipeline; the power generation device is electrically connected with the heating device and is used for supplying power to the heating device; compared with the prior art, the invention adopts the electric-heat conversion to improve the steam quality from the perspective of independent steam supply and heating of nuclear energy, further utilizes waste heat and makes an important contribution to carbon emission reduction.
Description
Technical Field
The invention relates to the field of nuclear power heat supply, in particular to a nuclear energy steam supply system.
Background
Industrial production requires large quantities of steam and fossil energy is an important source for providing steam to industrial users, such as by extraction from thermal power plants or self-contained boiler supplies. The use of fossil energy is difficult to avoid the emission of carbon oxides, which affects the environment, and carbon emission reduction becomes a focus of more attention under the background of carbon neutralization. Clean energy is an important and direct means for carbon emission reduction, but cannot be widely used for providing stable high-temperature stable industrial steam. The nuclear energy is used as clean, efficient and stable energy, can continuously provide heat for users, the safe and advanced pressurized water reactor technology is widely adopted by the nuclear energy at home and abroad at present, the energy supply type is mainly power supply, and the nuclear energy heat supply gradually becomes another energy supply type of the nuclear energy. At present, a pressurized water reactor nuclear power technology is mainly adopted, steam parameters are limited to a certain extent, and the steam extraction and heat supply of a nuclear power turbine cannot meet the requirement of a user on high-temperature steam. In addition, leakage of radioactivity from steam generator tubes with a very low probability is undesirable.
Accordingly, there remains a need in the art for improvements.
Disclosure of Invention
The invention aims to solve the problems of insufficient steam supply parameters and low safety and reliability in the prior art.
In order to achieve the purpose, the invention adopts the following technical scheme:
the invention provides a nuclear energy steam supply system, comprising:
nuclear reactor coolant piping;
the nuclear energy reactor coolant flows out of the nuclear energy reactor, enters the heat supply side of the heat exchange device through a pipeline and then returns to the nuclear energy reactor through the pipeline;
the system comprises a water supply pipe, a heat exchange device, a low-temperature steam pipe, a heating device, a power generation device and a water supply pipe, wherein the water supply pipe is connected with the heat exchange device and the heat exchange device through a pipeline;
the power generation device is electrically connected with the heating device and is used for supplying power to the heating device.
Furthermore, the heat exchange device comprises a first heat exchanger and a second heat exchanger which are connected in series, the nuclear energy reactor coolant enters the heat supply side of the first heat exchanger through a pipeline and then returns to the nuclear energy reactor through the pipeline, the heated side of the first heat exchanger and the heated side of the second heat exchanger are connected through an intermediate loop, and the to-be-heated feed water flows into the heated side of the second heater through a feed water pipeline and then is converted into low-temperature steam.
And the low-temperature steam flows through the power generation device and the heat supply side rear outflow system of the heat supply network heat exchanger in sequence, and the heat supply network water supply pipeline flows into the heat supply side rear of the heat supply network heat exchanger and is converted into a heat supply network water supply and outflow system.
Furthermore, the power generation device comprises a backpressure steam turbine, and a steam inlet of the backpressure steam turbine is provided with a steam supply isolation valve.
The invention has the beneficial effects that: from the perspective of independent steam supply and heating of nuclear energy, the steam quality is improved by adopting electric-heat conversion, waste heat is further utilized, and important contribution is made to regional carbon emission reduction.
Drawings
Fig. 1 is a schematic diagram of a system structure provided by the present invention.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and examples. It is to be understood that the specific embodiments described herein are merely illustrative of the invention and are not limiting of the invention. It should be further noted that, for the convenience of description, only some of the structures related to the present invention are shown in the drawings, not all of the structures.
In the description of the present invention, unless expressly stated or limited otherwise, the terms "connected," "connected," and "fixed" are to be construed broadly, e.g., as meaning permanently connected, removably connected, or integral to one another; can be mechanically or electrically connected; either directly or indirectly through intervening media, either internally or in any other relationship. The specific meanings of the above terms in the present invention can be understood in specific cases to those skilled in the art.
In the present invention, unless otherwise expressly stated or limited, "above" or "below" a first feature means that the first and second features are in direct contact, or that the first and second features are not in direct contact but are in contact with each other via another feature therebetween. Also, the first feature being "on," "above" and "over" the second feature includes the first feature being directly on and obliquely above the second feature, or merely indicating that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature includes the first feature being directly under and obliquely below the second feature, or simply meaning that the first feature is at a lesser elevation than the second feature.
In the description of the present embodiment, the terms "upper", "lower", "right", etc. are used in an orientation or positional relationship based on that shown in the drawings only for convenience of description and simplicity of operation, and do not indicate or imply that the device or element referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus, should not be construed as limiting the present invention. Furthermore, the terms "first" and "second" are used only for descriptive purposes and are not intended to have a special meaning.
As shown in fig. 1, the present invention provides a nuclear energy steam supply system, including:
nuclear reactor coolant piping;
the nuclear energy reactor coolant flows out of the nuclear energy reactor 1, enters the heat supply side of the heat exchange device through the reactor coolant pipeline hot section 4, and then returns to the nuclear energy reactor 1 through the reactor coolant pipeline cold section 3;
the system comprises a water supply pipe, a heat exchange device, a low-temperature steam pipe, a heating device, a power generation device and a water supply pipe, wherein the water supply pipe is connected with the heat exchange device and the heat exchange device through a pipeline;
the power generation device is electrically connected with the heating device and is used for supplying power to the heating device.
Further, the heat exchange device comprises a first heat exchanger 5 and a second heat exchanger 9 which are connected in series, the nuclear energy reactor coolant enters the heat supply side of the first heat exchanger 5 through a pipeline and then returns to the nuclear energy reactor 1 through a pipeline, the heated side of the first heat exchanger 5 and the heated side of the second heat exchanger 9 are connected through an intermediate loop, and the to-be-heated feed water flows into the heated side of the second heater 9 through a feed water pipeline and then is converted into low-temperature steam.
Further, the low-temperature steam generating set further comprises a heat supply network heat exchanger 19 and a heat supply network water supply pipeline 21, the other path of low-temperature steam sequentially flows through the generating set and the heat supply side rear outflow system of the heat supply network heat exchanger 19, and the heat supply network water supply pipeline 21 flows into the heat supply side rear of the heat supply network heat exchanger 19 and then is converted into heat supply network water supply 23 and flows out of the system.
Further, the power generation device comprises a back pressure turbine 15, and a steam supply isolation valve 14 is arranged at a steam inlet of the back pressure turbine 15.
During power operation of the plant, heat from the nuclear reactor 1 is transferred to the intermediate circuit via the reactor coolant loop cold leg 3, the reactor coolant loop hot leg 4 and the first heat exchanger 5, driven by the reactor coolant pump 2. The heat of the first heat exchanger 5 is transferred to the feed water line by means of the intermediate circuit circulation pump 6, the cold section 7 of the intermediate circuit, the hot section 8 of the intermediate circuit and the second heat exchanger 9. The feed water 10 is heated to low-temperature superheated steam in the second heat exchange 9, the low-temperature superheated steam enters a low-temperature steam pipeline 11 and a steam isolation valve 12, and part of the steam enters a backpressure steam turbine 15 to do work and generate power after passing through a backpressure steam turbine steam supply pipeline 13 and a backpressure steam turbine steam supply isolation valve 14. Another part of the steam passes through a heating device inlet isolation valve 16 and a heating device 17, the heating device 17 is powered by the power generation of the back pressure turbine 15, and the low-temperature steam is heated into high-temperature steam 18 in the heating device 17 and is supplied to an external user.
The exhaust steam from the back pressure turbine 15 enters a heating heater 19, and a heating network backwater 21 is heated to a heating network supply water 23 in the heating heater 19 after being driven by a heating network water pump 22. The drain water 20 having passed through the heating heater 19 is continuously recycled. The waste heat is further utilized, and the carbon emission is reduced.
It is to be noted that the foregoing is only illustrative of the preferred embodiments of the present invention and the technical principles employed. It will be understood by those skilled in the art that the present invention is not limited to the particular embodiments described herein, but is capable of various obvious changes, rearrangements and substitutions as will now become apparent to those skilled in the art without departing from the scope of the invention. Therefore, although the present invention has been described in greater detail by the above embodiments, the present invention is not limited to the above embodiments, and may include other equivalent embodiments without departing from the spirit of the present invention, and the scope of the present invention is determined by the scope of the appended claims.
Claims (4)
1. A nuclear energy steam supply system, comprising:
nuclear reactor coolant piping;
the nuclear energy reactor coolant flows out of the nuclear energy reactor, enters the heat supply side of the heat exchange device through a pipeline and then returns to the nuclear energy reactor through the pipeline;
the system comprises a water supply pipe, a heat exchange device, a low-temperature steam pipe, a heating device, a power generation device and a water supply pipe, wherein the water supply pipe is connected with the heat exchange device and the heat exchange device through a pipeline;
the power generation device is electrically connected with the heating device and is used for supplying power to the heating device.
2. The nuclear energy steam supply system according to claim 1, wherein the heat exchange device comprises a first heat exchanger and a second heat exchanger which are connected in series, the nuclear energy reactor coolant enters a heat supply side of the first heat exchanger through a pipeline and then returns to the nuclear energy reactor through a pipeline, a heated side of the first heat exchanger and a heated side of the second heat exchanger are connected through an intermediate loop, and the to-be-heated feedwater flows into a heated side of the second heater through a feedwater pipeline and then is converted into low-temperature steam.
3. The nuclear energy steam supply system according to claim 1, further comprising a heat supply network heat exchanger and a heat supply network water supply pipeline, wherein the other path of low-temperature steam flows through the power generation device and the heat supply side of the heat supply network heat exchanger in sequence and flows out of the system, and the heat supply network water supply pipeline flows into the heat supply side of the heat supply network heat exchanger and then is converted into heat supply network water supply and flows out of the system.
4. The nuclear power steam supply system of claim 1, wherein the power generation device comprises a back pressure turbine, and a steam supply isolation valve is arranged at a steam inlet of the back pressure turbine.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110368638.0A CN113113161A (en) | 2021-04-06 | 2021-04-06 | Nuclear energy steam supply system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110368638.0A CN113113161A (en) | 2021-04-06 | 2021-04-06 | Nuclear energy steam supply system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN113113161A true CN113113161A (en) | 2021-07-13 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110368638.0A Pending CN113113161A (en) | 2021-04-06 | 2021-04-06 | Nuclear energy steam supply system |
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| CN (1) | CN113113161A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115512866A (en) * | 2022-10-18 | 2022-12-23 | 浙江城建煤气热电设计院股份有限公司 | Multi-parameter long-distance nuclear energy steam supply system |
-
2021
- 2021-04-06 CN CN202110368638.0A patent/CN113113161A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115512866A (en) * | 2022-10-18 | 2022-12-23 | 浙江城建煤气热电设计院股份有限公司 | Multi-parameter long-distance nuclear energy steam supply system |
| CN115512866B (en) * | 2022-10-18 | 2023-08-11 | 浙江城建煤气热电设计院股份有限公司 | Multi-parameter long-distance nuclear energy steam supply system |
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| PB01 | Publication | ||
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |