CN113744899A - Starting heating system of nuclear reactor - Google Patents
Starting heating system of nuclear reactor Download PDFInfo
- Publication number
- CN113744899A CN113744899A CN202110613923.4A CN202110613923A CN113744899A CN 113744899 A CN113744899 A CN 113744899A CN 202110613923 A CN202110613923 A CN 202110613923A CN 113744899 A CN113744899 A CN 113744899A
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- China
- Prior art keywords
- core
- heating
- reactor
- heat
- pipeline
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Links
- 238000010438 heat treatment Methods 0.000 title claims abstract description 37
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 18
- 239000002826 coolant Substances 0.000 claims abstract description 11
- 238000002347 injection Methods 0.000 claims description 12
- 239000007924 injection Substances 0.000 claims description 12
- 238000002955 isolation Methods 0.000 claims description 3
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000008707 rearrangement Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
Images
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
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
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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
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
-
- 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
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structures Of Non-Positive Displacement Pumps (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention relates to the field of nuclear power, in particular to a starting heating system of a nuclear reactor, which is used for heating coolant in a housing of the nuclear reactor and is characterized by comprising a heat input device, a heating device and a control device, wherein the heat input device is used for conveying high-temperature heat medium to a reactor core through a heating pipeline so as to heat the coolant of the reactor; a water return pipeline is connected between the reactor core and the heat input device, and the low-temperature heat medium flows back to the heat input device through the water return pipeline; one end of the heating pipeline, which is positioned at the reactor core, is higher than one end of the water return pipeline, which is positioned at the reactor core; a heat exchanger disposed in the housing and connected to the external circuit through a pipe to conduct heat to the external circuit; compared with the prior art, the invention can meet the temperature rise requirement of the coolant before the full natural circulation nuclear reactor reaches the critical temperature, ensure certain natural circulation and ensure the safe startup of the reactor.
Description
Technical Field
The invention relates to the field of nuclear power, in particular to a starting heating system of a nuclear reactor.
Background
Generally, the nuclear reactor is started by adopting a hot start scheme, and the temperature of a coolant must be increased to a hot standby state before the nuclear reactor core reaches a critical state. For a nuclear reactor without a main pump and with full natural circulation, the temperature cannot be raised by depending on the main pump to do work like a traditional nuclear power plant, and other starting heating schemes need to be considered.
Accordingly, there remains a need in the art for improvements.
Disclosure of Invention
The invention aims to solve the problem that the temperature of a reactor core cannot be raised by applying work through a main pump in the prior art.
In order to achieve the purpose, the invention adopts the following technical scheme:
a startup heating system for a nuclear reactor for heating reactor coolant in a housing of the nuclear reactor, comprising:
a heat input device for conveying a high-temperature heat medium to the core through a heating pipeline so as to heat the coolant in the casing;
a water return pipeline is connected between the reactor core and the heat input device, and the low-temperature heat medium flows back to the heat input device through the water return pipeline;
one end of the heating pipeline, which is positioned at the reactor core, is higher than one end of the water return pipeline, which is positioned at the bottom of the housing and is lower than the reactor core;
and the heat exchanger is arranged in the housing and is connected with the external loop through a pipeline so as to lead out heat to the external loop.
Further, the core is connected with the housing through a core barrel.
Furthermore, the heat input device comprises an injection pump and an auxiliary heating exchanger, the output end of the injection pump is connected with the input end of the auxiliary heating exchanger through a pipeline, and the output end of the auxiliary heating exchanger outputs high-temperature heat medium to the upper part of the reactor core through the heating pipeline.
Furthermore, one end of the water return pipeline is arranged below the reactor core, and the other end of the water return pipeline is connected with the injection pump and used for conveying the low-temperature heat medium below the reactor core into the injection pump through the water return pipeline so as to form a circulation loop.
Furthermore, an isolation valve is arranged on the heating pipeline.
The invention has the beneficial effects that: the method can meet the temperature rise requirement of the coolant before the full natural circulation nuclear reactor reaches the critical temperature, ensure certain natural circulation and ensure the safe startup of the reactor.
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 startup heating system for a nuclear reactor, which heats coolant in a housing 2 containing a core 3, the startup heating system including:
a heat input device for delivering a high-temperature heat medium to the core 3 through a heating line to warm the coolant in the housing 2;
a water return pipeline is also connected between the reactor core 3 and the heat input device, and the low-temperature heat medium flows back to the heat input device through the water return pipeline;
one end of the heating pipeline, which is positioned at the reactor core 3, is higher than one end of the water return pipeline, which is positioned at the bottom of the housing 2 and is lower than the reactor core;
and a heat exchanger 4 arranged in the casing 2 and connected to the external circuit by a pipe to conduct heat to the external circuit.
Further, the core 3 is connected to the housing 2 through a core barrel.
Further, the heat input device comprises an injection pump 1-1 and an auxiliary heating exchanger 1-2, the output end of the injection pump 1-1 is connected with the input end of the auxiliary heating exchanger 1-2 through a pipeline, and the output end of the auxiliary heating exchanger 1-2 outputs a high-temperature heat medium to the upper part of the reactor core 3 through the heating pipeline.
Furthermore, one end of the water return pipeline is arranged below the reactor core 3, and the other end of the water return pipeline is connected with the injection pump 1-1, and is used for conveying the low-temperature thermal medium below the reactor core 3 to the injection pump 1-1 through the water return pipeline to form a circulation loop.
Furthermore, an isolation valve 5 is arranged on the heating pipeline.
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 (5)
1. A nuclear reactor startup heating system for heating coolant in a nuclear reactor enclosure containing a core, comprising:
a heat input device for conveying a high-temperature heat medium to the core through a heating pipeline so as to heat the coolant in the casing;
a water return pipeline is connected between the reactor core and the heat input device, and the low-temperature heat medium flows back to the heat input device through the water return pipeline;
one end of the heating pipeline, which is positioned at the reactor core, is higher than one end of the water return pipeline, which is positioned at the bottom of the housing and is lower than the reactor core;
and the heat exchanger is arranged in the housing and is connected with the external loop through a pipeline so as to lead out heat to the external loop.
2. The nuclear reactor startup heating system of claim 1, wherein the core is connected to the enclosure by a core barrel.
3. The startup heating system of a nuclear reactor according to claim 1, wherein the heat input means includes an injection pump and an auxiliary heat exchanger, an output end of the injection pump is connected to an input end of the auxiliary heat exchanger through a pipe, and an output end of the auxiliary heat exchanger outputs a high-temperature heat medium to an upper portion of the core through the heating pipe.
4. The startup heating system of a nuclear reactor according to claim 3, wherein one end of the return pipe is provided below the core, and the other end thereof is connected to the injection pump, for conveying the low-temperature thermal medium below the core into the injection pump through the return pipe to form a circulation loop.
5. A start-up heating system for a nuclear reactor as claimed in claim 3, in which the heating line is provided with an isolation valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110613923.4A CN113744899B (en) | 2021-06-02 | 2021-06-02 | Nuclear reactor start-up heating system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110613923.4A CN113744899B (en) | 2021-06-02 | 2021-06-02 | Nuclear reactor start-up heating system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN113744899A true CN113744899A (en) | 2021-12-03 |
| CN113744899B CN113744899B (en) | 2024-06-18 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110613923.4A Active CN113744899B (en) | 2021-06-02 | 2021-06-02 | Nuclear reactor start-up heating system |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114420330A (en) * | 2022-01-28 | 2022-04-29 | 上海核工程研究设计院有限公司 | Full natural circulation integrated reactor inlet and outlet temperature measuring device |
| CN115050491A (en) * | 2022-06-24 | 2022-09-13 | 中国核动力研究设计院 | Full-pressure type auxiliary heating and boosting system and method for small modular reactor |
Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1999059160A1 (en) * | 1998-05-12 | 1999-11-18 | Ansaldo Energia S.P.A. | Cooling system for a nuclear reactor |
| US20130336441A1 (en) * | 2012-06-13 | 2013-12-19 | Westinghouse Electric Company Llc | Small modular reactor safety systems |
| CN103477394A (en) * | 2011-02-15 | 2013-12-25 | 纽斯高动力有限责任公司 | Heat removal system and method for use with a nuclear reactor |
| CN103928064A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | Thermally-operated conversion system |
| CN105810257A (en) * | 2014-12-29 | 2016-07-27 | 国核华清（北京）核电技术研发中心有限公司 | Pressure release condensation heat transfer system for passive nuclear power station |
| CN108550407A (en) * | 2018-03-30 | 2018-09-18 | 清华大学天津高端装备研究院 | A kind of lead bismuth heap primary Ioops system and nuclear reactor |
| CN108648837A (en) * | 2018-05-15 | 2018-10-12 | 中国核动力研究设计院 | A kind of modular Small reactor of full Natural Circulation |
| CN110010255A (en) * | 2019-04-08 | 2019-07-12 | 南华大学 | A kind of Lead cooled fast breeder reactor residual heat removal system and discharge method |
| CN110617470A (en) * | 2019-10-12 | 2019-12-27 | 清华大学 | Superheated steam production system and superheated steam production method |
| CN215450908U (en) * | 2021-06-02 | 2022-01-07 | 上海核工程研究设计院有限公司 | Starting heating system of nuclear reactor |
-
2021
- 2021-06-02 CN CN202110613923.4A patent/CN113744899B/en active Active
Patent Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1999059160A1 (en) * | 1998-05-12 | 1999-11-18 | Ansaldo Energia S.P.A. | Cooling system for a nuclear reactor |
| CN103477394A (en) * | 2011-02-15 | 2013-12-25 | 纽斯高动力有限责任公司 | Heat removal system and method for use with a nuclear reactor |
| US20130336441A1 (en) * | 2012-06-13 | 2013-12-19 | Westinghouse Electric Company Llc | Small modular reactor safety systems |
| CN103928064A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | Thermally-operated conversion system |
| CN105810257A (en) * | 2014-12-29 | 2016-07-27 | 国核华清（北京）核电技术研发中心有限公司 | Pressure release condensation heat transfer system for passive nuclear power station |
| CN108550407A (en) * | 2018-03-30 | 2018-09-18 | 清华大学天津高端装备研究院 | A kind of lead bismuth heap primary Ioops system and nuclear reactor |
| CN108648837A (en) * | 2018-05-15 | 2018-10-12 | 中国核动力研究设计院 | A kind of modular Small reactor of full Natural Circulation |
| CN110010255A (en) * | 2019-04-08 | 2019-07-12 | 南华大学 | A kind of Lead cooled fast breeder reactor residual heat removal system and discharge method |
| CN110617470A (en) * | 2019-10-12 | 2019-12-27 | 清华大学 | Superheated steam production system and superheated steam production method |
| CN215450908U (en) * | 2021-06-02 | 2022-01-07 | 上海核工程研究设计院有限公司 | Starting heating system of nuclear reactor |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114420330A (en) * | 2022-01-28 | 2022-04-29 | 上海核工程研究设计院有限公司 | Full natural circulation integrated reactor inlet and outlet temperature measuring device |
| CN115050491A (en) * | 2022-06-24 | 2022-09-13 | 中国核动力研究设计院 | Full-pressure type auxiliary heating and boosting system and method for small modular reactor |
| CN115050491B (en) * | 2022-06-24 | 2024-05-07 | 中国核动力研究设计院 | Full-pressure type auxiliary temperature and pressure increasing system and method for small modular stack |
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| Publication number | Publication date |
|---|---|
| CN113744899B (en) | 2024-06-18 |
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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. |
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| GR01 | Patent grant |