CN114038591A - Primary side passive residual heat removal system for nuclear reactor - Google Patents
Primary side passive residual heat removal system for nuclear reactor Download PDFInfo
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- CN114038591A CN114038591A CN202111456131.7A CN202111456131A CN114038591A CN 114038591 A CN114038591 A CN 114038591A CN 202111456131 A CN202111456131 A CN 202111456131A CN 114038591 A CN114038591 A CN 114038591A
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- 239000000498 cooling water Substances 0.000 claims abstract description 37
- 238000002955 isolation Methods 0.000 claims abstract description 30
- 239000003381 stabilizer Substances 0.000 claims abstract description 11
- 238000012544 monitoring process Methods 0.000 claims abstract description 5
- 239000011148 porous material Substances 0.000 claims description 40
- 239000013535 sea water Substances 0.000 claims description 22
- 239000002826 coolant Substances 0.000 claims description 17
- 238000012546 transfer Methods 0.000 claims description 16
- 239000002918 waste heat Substances 0.000 abstract description 9
- 238000000034 method Methods 0.000 description 6
- 230000008676 import Effects 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 238000004891 communication Methods 0.000 description 2
- 238000007599 discharging Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000009795 derivation Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 238000005381 potential energy Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 230000001960 triggered effect Effects 0.000 description 1
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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
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a primary side passive waste heat discharge system for a nuclear reactor, which comprises a reactor, a cooling water tank, an inlet pipeline, an outlet pipeline, a heat exchanger and a control unit, wherein the cooling water tank is arranged in the reactor; the heat exchanger is positioned in the cooling water tank, one end of the inlet pipeline is connected with the reactor, the other end of the inlet pipeline penetrates through the cooling water tank to be connected with an inlet of the heat exchanger, one end of the outlet pipeline is connected with an outlet of the heat exchanger and penetrates through the cooling water tank to be connected with the reactor, the inlet and the outlet of the heat exchanger are both higher than the outlet and the inlet of the reactor, which are connected with the inlet pipeline and the outlet pipeline, an isolation valve A is arranged at the part of the outlet pipeline, which is positioned between the cooling water tank and the reactor, and the control unit is connected with the isolation valve A; the pressure stabilizer is used for monitoring the pressure value of the reactor and transmitting the pressure value to the control unit; when the reactor is shut down and the pressure value of the reactor is reduced to a set value, the isolating valve A is opened to form a first heat exchange circulating loop. Heat can be removed by utilizing a passive mode, external force is not needed, and the heat-removing heat-using external force can still be used under the condition of losing power supply.
Description
Technical Field
The invention relates to the technical field of nuclear reactor safety, in particular to a primary side passive waste heat removal system for a nuclear reactor.
Background
During a nuclear reaction, a scram may occur for several reasons. The problem of guiding out decay heat after the nuclear reactor is shut down is a key problem related to the safety of the nuclear reactor, and particularly when a ship reactor has a whole ship power-off accident, the reactor loses an active waste heat discharge system, and if the decay heat of the reactor core cannot be safely guided out, serious accidents such as the melting of the reactor core and the like can be caused. Therefore, other related safety systems need to be arranged to solve the problem of the derivation of the core decay heat under the condition of the whole ship power failure or other heat conduction path loss conditions. Compared with a land-based reactor, the space of a cabin of a marine reactor is limited, and how to utilize the limited space to maximally discharge heat is also an urgent problem to be solved.
Disclosure of Invention
The invention aims to solve the technical problems of maximally discharging heat by using a limited space of a cabin and guiding out the decay heat of a reactor core under the working condition of power failure of a whole ship or loss of other heat conduction paths, and provides a primary side passive waste heat discharging system for a nuclear reactor, which solves the technical problem of guiding out the decay heat after the nuclear reactor is shut down.
The invention is realized by the following technical scheme:
a primary side passive residual heat removal system for a nuclear reactor comprises a reactor, a cooling water tank, an inlet pipeline, an outlet pipeline, a heat exchanger and a control unit;
the heat exchanger is positioned in the cooling water tank, one end of the inlet pipeline is connected with the reactor, the other end of the inlet pipeline penetrates through the cooling water tank to be connected with an inlet of the heat exchanger, one end of the outlet pipeline is connected with an outlet of the heat exchanger and penetrates through the cooling water tank to be connected with the reactor, the inlet and the outlet of the heat exchanger are both higher than the outlet and the inlet of the reactor, which are connected with the inlet pipeline and the outlet pipeline, an isolation valve A is arranged at the part of the outlet pipeline, which is positioned between the cooling water tank and the reactor, and the control unit is connected with the isolation valve A;
a reactor heat pipeline between the inlet pipeline and the reactor is also provided with a voltage stabilizer, and the voltage stabilizer is used for monitoring the pressure value of the reactor and transmitting the pressure signal to the control unit;
when the reactor is shut down and the pressure value of the reactor received by the control unit is reduced to a set value, the control unit controls the isolation valve A to be opened to form a first heat exchange circulation loop in which the coolant enters the heat exchanger through the inlet pipeline and returns to the reactor after heat exchange.
Optionally, the heat transfer portion on the heat exchanger is of an arc-shaped structure.
Optionally, the inlet end of the heat exchanger is vertically higher than the outlet end thereof.
Optionally, reactor, coolant tank all are located and hold the body, and the inside wall that holds the body is the arc curved surface, and coolant tank fixes on the inside wall that holds the body, and the arc curved surface of the last heat transfer portion of heat exchanger cooperatees with the arc curved surface that holds the body.
Optionally, the containment body is a hold.
Optionally, the accommodating body is located in seawater, the accommodating body is further provided with a plurality of inflow pore channels and outflow pore channels, each inflow pore channel and each outflow pore channel are located between the joints of the cooling water tank and the accommodating body to form a second heat exchange circulation loop in which seawater enters the cooling water tank through the inflow pore channels and flows out through the outflow pore channels, each inflow pore channel and each outflow pore channel are provided with an isolation valve B, each isolation valve B is connected with the control unit, and each inflow pore channel is higher than each corresponding outflow pore channel. (ii) a
When the reactor is shut down and the pressure value of the reactor received by the control unit is reduced to a set value, the control unit controls the isolation valve B to be opened.
Alternatively, one inflow port and one outflow port are provided.
Compared with the prior art, the invention has the following advantages and beneficial effects:
(1) the embodiment of the invention provides a primary side passive residual heat removal system for a nuclear reactor, which is provided with a cooling water tank and a heat exchanger, and an inlet pipeline and an outlet pipeline are respectively and directly connected with an inlet and an outlet of the reactor, so that the reactor keeps the same pressure state of the inlet pipeline, the heat exchanger and the reactor system under the normal operation condition, and enough thermal driving pressure is kept, once an accident working condition such as emergency shutdown occurs and the pressure of the reactor is monitored to be reduced to a certain value, the passive residual heat removal system starts to be put into operation, an isolation valve A is opened, a coolant in the reactor can be driven to spontaneously enter the heat exchanger for heat exchange by pressure by utilizing the pre-established thermal driving pressure, and because the inlet and the outlet of the heat exchanger are higher than the outlet and the inlet which are connected with the inlet pipeline and the outlet pipeline of the reactor, the coolant after heat exchange can return to the reactor by means of self gravity, and then the subsequent circulating heat exchange process is carried out. Therefore, heat can be removed by utilizing a passive mode without external force or pump driving, and the heat-removing device can still be used under the condition of power loss.
(2) According to the primary side passive residual heat removal system for the nuclear reactor, provided by the embodiment of the invention, the heat transfer part arranged on the heat exchanger is of an arc-shaped tubular structure, and the inlet end of the heat exchanger is higher than the outlet end of the heat exchanger in the vertical direction, so that the whole heat exchanger is obliquely arranged above the reactor. The arc-shaped tubular structure can be combined with the arc-shaped curved surface of the side wall of the cabin to the maximum extent, the limited space is fully utilized, and the inlet end and the outlet end of the heat exchanger form the maximum natural circulation potential difference, so that the maximum natural circulation driving force is realized, the higher waste heat discharge capacity is ensured, and the normal operation of the first heat exchange circulation loop is ensured. And the arc structure of the heat transfer part of the heat exchanger can also increase the heat exchange area and improve the heat conduction efficiency.
(3) The primary side passive residual heat removal system for the nuclear reactor provided by the embodiment of the invention is provided with an inflow pore channel and an outflow pore channel, wherein the inflow pore channel and the outflow pore channel are respectively positioned between the connecting parts of the cooling water tank and the accommodating body, the outflow pore channel is higher than the inflow pore channel, and the inflow pore channel and the outflow pore channel are provided with isolation valves B. After the passive residual heat removal system is put into operation, seawater enters from the inflow pore channel at the lower part, exchanges heat with the heat exchanger and then flows out from the outflow pore channel at the upper part, and the seawater is driven by the natural potential energy of the seawater to complete the seawater heat exchange circulation. The seawater is used as a final heat trap, and heat can be continuously introduced into the sea. And the height of the inlet end and the outlet end of the heat exchanger can provide good potential difference for the circulating flow of the seawater, so that the natural circulation capacity of the seawater side is improved. The heat conduction can be carried out without external force and under the passive condition. Still usable in the event of loss of power.
(4) The primary side passive residual heat removal system for the nuclear reactor provided by the embodiment of the invention can effectively prevent a seawater circulation loop from generating instability to cause the reduction of residual heat removal capability when the cabin works under a lower pressure condition without power failure. And a voltage stabilizer is arranged to monitor the pressure of the reactor in real time and realize the timely feedback of the state.
(5) The primary side passive residual heat removal system for the nuclear reactor provided by the embodiment of the invention has a compact overall structure arrangement, can effectively reduce the volume and save the space.
Drawings
In order to more clearly illustrate the technical solutions of the exemplary embodiments of the present invention, the drawings that are required to be used in the embodiments will be briefly described below, it should be understood that the following drawings only illustrate some embodiments of the present invention and therefore should not be considered as limiting the scope, and that for those skilled in the art, other related drawings can be obtained from these drawings without inventive effort. In the drawings:
fig. 1 is a schematic diagram of a primary-side passive residual heat removal system for a nuclear reactor according to an embodiment of the present invention.
Reference numbers and corresponding part names in the drawings:
1-reactor, 2-heat exchanger, 3-cooling water tank, 4-isolation valve A, 5-isolation valve B, 6-cabin, 7-seawater, 8-voltage stabilizer, 9-inlet pipeline, 10-outlet pipeline and 11-reactor heat pipeline.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention. However, it will be apparent to one of ordinary skill in the art that: it is not necessary to employ these specific details to practice the present invention. In other instances, well-known structures, circuits, materials, or methods have not been described in detail so as not to obscure the present invention.
Throughout the specification, reference to "one embodiment," "an embodiment," "one example," or "an example" means: the particular features, structures, or characteristics described in connection with the embodiment or example are included in at least one embodiment of the invention. Thus, the appearances of the phrases "one embodiment," "an embodiment," "one example" or "an example" in various places throughout this specification are not necessarily all referring to the same embodiment or example. Furthermore, the particular features, structures, or characteristics may be combined in any suitable combination and/or sub-combination in one or more embodiments or examples. Further, those of ordinary skill in the art will appreciate that the illustrations provided herein are for illustrative purposes and are not necessarily drawn to scale. As used herein, the term "and/or" includes any and all combinations of one or more of the associated listed items.
In the description of the present invention, the terms "front", "rear", "left", "right", "upper", "lower", "vertical", "horizontal", "upper", "lower", "inner", "outer", etc. indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience of description and simplicity of description, but do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed in a particular orientation, and be operated, and therefore, should not be construed as limiting the scope of the present invention.
Examples
A primary side passive residual heat removal system for a nuclear reactor 1 comprises a reactor 1, a cooling water tank 3, an inlet pipeline 9, an outlet pipeline 10, a heat exchanger 2 and a control unit.
Heat exchanger 2 fixed mounting is in cooling water tank 3's inside, the export that corresponds on the one end fixed connection reactor 1 of inlet pipeline 9, the other end passes cooling water tank 3 fixed connection heat exchanger 2's import, the export of the one end fixed connection heat exchanger 2 of outlet pipeline 10, and pass corresponding entry on cooling water tank 3 fixed connection reactor 1, outlet pipeline 10 is equipped with isolating valve A4 in the part department that is located cooling water tank 3 and reactor 1, the work of control unit electricity connection or communication connection isolating valve A4 and control isolating valve A4, the fixed heat transfer portion that is provided with between heat exchanger 2's import and the export, be used for carrying out thermal conduction, the exchange, the heat transfer portion on heat exchanger 2 sets up to the arc structure, increase heat conduction area, improve heat transfer efficiency. A pressure stabilizer 8 is further arranged on a reactor heat pipeline 11 between the inlet pipeline 9 and the reactor 1, and the pressure stabilizer 8 is used for monitoring the pressure value of the reactor 1 and transmitting the pressure value signal to the control unit. A reactor cold pipe 12 is provided on the reactor corresponding to the reactor hot pipe 11.
When the reactor 1 stops, the active waste heat discharge system of a loop is put into operation firstly, reactor core decay heat is led out, the pressure in the reactor is monitored in real time by the voltage stabilizer 8, signals are transmitted to the control unit, the control unit compares the received pressure value with the set value, when the pressure value of the reactor 1 is reduced to the set value (3-4 Mpa), the passive waste heat discharge system is put into use, the control unit controls the isolation valve A4 to be opened, the coolant enters the heat exchanger 2 through the inlet pipeline 9, the coolant after heat exchange returns to the reactor 1 again, a first heat exchange circulation loop is formed, the operation can be carried out in a reciprocating mode until the reactor 1 reaches a safe state, and the control unit controls the isolation valve A4 to be closed.
In one or more embodiments, the inlet and the outlet of the heat exchanger 2 are arranged higher than the inlet and the outlet of the reactor 1 connected with the inlet pipeline 9 and the outlet pipeline 10, and the inlet end of the heat exchanger 2 is arranged higher than the outlet end thereof in the vertical direction. Because the inlet pipeline 9 is directly connected with the coolant system of the reactor 1, the heat exchanger 2 and the reactor 1 system are in the same pressure state, and because the heat quantity is higher in the normal operation process of the reactor 1, the temperature of the inlet pipeline 9 directly connected with the reactor is also higher, and the water temperature of the inlet pipeline 9 is higher than that of the outlet pipeline 10, so that a sufficient thermal driving head is kept between the reactor 1 and the inlet pipeline 9 and the outlet pipeline 10 during the normal operation of the reactor 1.
During the normal operation of the reactor 1, because the temperature of the cooling water tank 3 and the outlet pipeline 10 is lower than that of the reactor 1, and a pressure difference exists, a part of the coolant in the reactor 1 enters the heat exchanger 2 through the inlet pipeline 9 and is cooled in the heat exchanger 2 during the operation of the reactor 1. The import and the export that set up heat exchanger 2 all are higher than reactor 1 and inlet line 9, the play that outlet line 10 is connected, the entry, even heat exchanger 2 is higher than the position of reactor 1, still can keep sufficient thermal drive pressure head during reactor 1 normal operating, and at reactor 1 abnormal operation, even the accident condition appears, rely on the thermal drive pressure head just can make the coolant in the reactor 1 enter into heat exchanger 2, and rely on self gravity just can return to in the reactor 1 in the heat exchanger 2 after the coolant heat transfer, ensure that the first heat circulation return circuit can normal operating under the condition of power loss or emergence accident condition.
In one or more embodiments, the heat transfer portion of the heat exchanger 2 is provided as an arc-shaped tubular structure, and the reactor 1 and the cooling water tank 3 are both located in a containing body, which is a cabin 6. The inner side wall of the cabin 6 is an arc-shaped curved surface, the cooling water tank 3 is fixed on the inner side wall of the cabin 6, the arc-shaped curved surface of the heat transfer part on the heat exchanger 2 is matched with the arc-shaped curved surface of the cabin 6, and the heat transfer part of the heat exchanger 2 is close to the side wall of the cabin 6 as much as possible, so that the space is saved to the maximum extent, and the arc-shaped structure of the heat transfer part can be utilized to the maximum extent to increase the heat transfer efficiency.
In one or more embodiments, the cabin 6 is located in the seawater 7, the cabin 6 is further provided with a plurality of inflow pore canals and outflow pore canals for the circulation of the seawater 7, each inflow pore canal and each outflow pore canal are respectively provided with an isolation valve B5 in a one-to-one correspondence manner, each isolation valve B5 is connected with the control unit, the control unit controls the opening and closing of the isolation valve B5, each inflow pore canal is higher than each outflow pore canal in the vertical height, and each inflow pore canal and each outflow pore canal are located between the two connecting ends of the cooling water tank 3 and the cabin 6. Preferably, the inflow opening and the outflow opening are respectively provided one, and the height of the outflow opening is located at the height of the inflow opening. After entering the cooling water tank 3 from the isolating valve of the inflow pore channel, the seawater 7 exchanges heat with the coolant in the heat exchanger 2, and then flows into the sea from the isolating valve of the outflow pore channel, and the seawater circulates back and forth in such a way, so that a seawater natural circulation loop, namely a second heat transfer circulation loop, is formed. When the reactor is shut down and the pressure value of the reactor received by the control unit is reduced to a set value, the control unit controls the isolation valve B5 to be opened until the reactor 1 reaches a safe state, and the control unit closes the isolation valve B5.
The working process of the primary side passive residual heat removal system for the nuclear reactor 1 provided by the embodiment of the invention is as follows:
under the normal operation condition of the reactor 1, the passive residual heat removal system is in a standby state, the isolation valve A4 and the isolation valve B5 are both in a closed state, the inlet pipeline 9 and the outlet pipeline 10 are connected with a coolant system of the reactor 1, the water temperature of the inlet pipeline 9 is higher than that of the outlet pipeline 10, the heat exchanger 2 is filled with coolant and is in the same pressure state as that of the reactor 1 system, and therefore a sufficient thermal driving head is established and maintained during the normal operation of the reactor 1.
Under the operating mode of accident, the emergency shutdown is triggered to 1 protection system of reactor, and kinetic energy waste heat discharge system on the return circuit at first carries out the heat extraction, treats that the pressure of monitoring in the stabiliser 8 drops to when 3 ~ 4MPa, and the control unit control isolation valve A4, each isolation valve B5 open, and passive waste heat discharge system puts into operation promptly, forms two natural circulation return circuits: the first heat exchange circulation loop is the natural circulation of the reactor 1 coolant of the tube pass of the reactor 1 and the heat exchanger 2, namely the coolant in the reactor 1 enters the heat exchanger 2 to exchange heat and automatically returns to the reactor 1, and flows out of the heat exchanger 2 again to form a circulation; the second heat exchange circulation loop is the natural circulation of the seawater in the cooling water tank 3, when the two isolation valves B5 are opened, the seawater 7 enters the cooling water tank 3 from the isolation valve corresponding to the inlet channel, is heated by the heat exchanger 2 for heat exchange, and then the seawater 7 flows into the sea from the isolation valve B5 corresponding to the outlet channel, so that the natural circulation loop of the seawater is formed.
The control unit may control the passive residual heat removal system through an electrical connection or a communication connection, and the power loss signal may be monitored, signal-converted, and retransmitted to the control unit through other hardware or hardware according to a related program, which is not described in detail herein.
It will be understood by those skilled in the art that all or part of the steps of the above facts and methods can be implemented by hardware related to instructions of a program, and the related program or the program can be stored in a computer readable storage medium, and when executed, the program includes the following steps: corresponding method steps are introduced here, and the storage medium may be a ROM/RAM, a magnetic disk, an optical disk, etc.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (7)
1. A primary side passive residual heat removal system for a nuclear reactor is characterized by comprising a reactor (1), a cooling water tank (3), an inlet pipeline (9), an outlet pipeline (10), a heat exchanger (2) and a control unit;
the heat exchanger (2) is positioned in the cooling water tank (3), one end of the inlet pipeline (9) is connected with the reactor (1), the other end of the inlet pipeline penetrates through the cooling water tank (3) and is connected with an inlet of the heat exchanger (2), one end of the outlet pipeline (10) is connected with an outlet of the heat exchanger (2) and penetrates through the cooling water tank (3) and is connected with the reactor (1), the inlet and the outlet of the heat exchanger (2) are higher than the inlet and the outlet of the reactor (1) which are connected with the inlet pipeline (9) and the outlet pipeline (10), an isolating valve A (4) is arranged at the part of the outlet pipeline (10) positioned between the cooling water tank (3) and the reactor (1), and the control unit is connected with the isolating valve A (4);
a pressure stabilizer (8) is further arranged on a reactor heat pipeline (11) between the inlet pipeline (9) and the reactor (1), and the pressure stabilizer (8) is used for monitoring the pressure value of the reactor (1) and transmitting the pressure signal to the control unit;
when the reactor is shut down and the pressure value of the reactor received by the control unit is reduced to a set value, the control unit controls the isolation valve A (4) to be opened, so that a first heat exchange circulation loop is formed, wherein the coolant enters the heat exchanger (2) through the inlet pipeline (9), exchanges heat and then returns to the reactor (1).
2. A primary side passive residual heat removal system for a nuclear reactor according to claim 1 characterized in that the heat transfer portion on the heat exchanger (2) is of an arc-shaped configuration.
3. A primary side passive residual heat removal system for a nuclear reactor according to claim 1, characterized in that the inlet end of the heat exchanger (2) is vertically higher than the outlet end thereof.
4. A primary side passive residual heat removal system for a nuclear reactor according to claim 3 wherein the reactor (1) and the cooling water tank (3) are both located in the housing, the inner side wall of the housing is an arc-shaped curved surface, the cooling water tank (3) is fixed on the inner side wall of the housing, and the arc-shaped curved surface of the heat transfer portion of the heat exchanger (2) is matched with the arc-shaped curved surface of the housing.
5. A primary side passive residual heat removal system for a nuclear reactor according to claim 4 characterized in that the containment is a hold (6).
6. The primary side passive residual heat removal system for the nuclear reactor according to claim 4, wherein the accommodating body is located in seawater (7), the accommodating body is further provided with a plurality of inflow pore canals and outflow pore canals, each inflow pore canal and each outflow pore canal are located between the connection part of the cooling water tank (3) and the accommodating body, a second heat exchange circulation loop is formed in which seawater (7) enters the cooling water tank (3) through the inflow pore canals and flows out through the outflow pore canals, each inflow pore canal and each outflow pore canal are provided with an isolation valve B (5), each isolation valve B (5) is connected with the control unit, and each inflow pore canal is higher than each corresponding outflow pore canal;
when the reactor is shut down and the pressure value of the reactor received by the control unit is reduced to a set value, the control unit controls the isolation valve B (5) to be opened.
7. The primary side passive residual heat removal system for a nuclear reactor of claim 6, wherein one of the inflow port and the outflow port is provided.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202111456131.7A CN114038591A (en) | 2021-12-01 | 2021-12-01 | Primary side passive residual heat removal system for nuclear reactor |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202111456131.7A CN114038591A (en) | 2021-12-01 | 2021-12-01 | Primary side passive residual heat removal system for nuclear reactor |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115083635A (en) * | 2022-06-28 | 2022-09-20 | 华能核能技术研究院有限公司 | Heat transfer system of gas cooled reactor |
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| CN103165200A (en) * | 2013-01-14 | 2013-06-19 | 上海核工程研究设计院 | Decay heat removal system of reactor |
| CN104733060A (en) * | 2015-03-25 | 2015-06-24 | 东南大学 | Passive residual heat removal system of marine nuclear power device |
| CN107799190A (en) * | 2017-11-14 | 2018-03-13 | 中国船舶重工集团公司第七〇九研究所 | A kind of pressurized water reactor peculiar to vessel and its primary side non-kinetic residual heat removal system |
| CN207909507U (en) * | 2017-10-31 | 2018-09-25 | 上海核工程研究设计院有限公司 | A kind of passive residual heat removal system |
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2021
- 2021-12-01 CN CN202111456131.7A patent/CN114038591A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103165200A (en) * | 2013-01-14 | 2013-06-19 | 上海核工程研究设计院 | Decay heat removal system of reactor |
| CN104733060A (en) * | 2015-03-25 | 2015-06-24 | 东南大学 | Passive residual heat removal system of marine nuclear power device |
| CN207909507U (en) * | 2017-10-31 | 2018-09-25 | 上海核工程研究设计院有限公司 | A kind of passive residual heat removal system |
| CN107799190A (en) * | 2017-11-14 | 2018-03-13 | 中国船舶重工集团公司第七〇九研究所 | A kind of pressurized water reactor peculiar to vessel and its primary side non-kinetic residual heat removal system |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN115083635A (en) * | 2022-06-28 | 2022-09-20 | 华能核能技术研究院有限公司 | Heat transfer system of gas cooled reactor |
| CN115083635B (en) * | 2022-06-28 | 2023-08-22 | 华能核能技术研究院有限公司 | Air-cooled reactor heat transfer system |
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