CN114038591B - Primary side passive waste heat discharging system for nuclear reactor - Google Patents
Primary side passive waste heat discharging system for nuclear reactor Download PDFInfo
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- CN114038591B CN114038591B CN202111456131.7A CN202111456131A CN114038591B CN 114038591 B CN114038591 B CN 114038591B CN 202111456131 A CN202111456131 A CN 202111456131A CN 114038591 B CN114038591 B CN 114038591B
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- reactor
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- water tank
- cooling water
- inlet
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- 239000002918 waste heat Substances 0.000 title abstract description 23
- 238000007599 discharging Methods 0.000 title abstract description 18
- 239000000498 cooling water Substances 0.000 claims abstract description 38
- 238000002955 isolation Methods 0.000 claims abstract description 36
- 239000003381 stabilizer Substances 0.000 claims abstract description 8
- 238000012544 monitoring process Methods 0.000 claims abstract description 3
- 239000011148 porous material Substances 0.000 claims description 24
- 239000013535 sea water Substances 0.000 claims description 20
- 239000002826 coolant Substances 0.000 claims description 16
- 238000012546 transfer Methods 0.000 claims description 15
- 238000000034 method Methods 0.000 description 7
- 238000005452 bending Methods 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 238000004891 communication Methods 0.000 description 2
- 238000000605 extraction Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000010586 diagram 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
Classifications
-
- 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
Landscapes
- 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 discharging 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 connected with 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 passes through the cooling water tank and is connected with the inlet of the heat exchanger, one end of the outlet pipeline is connected with the outlet of the heat exchanger and passes through the cooling water tank and is connected with the reactor, the inlet and the outlet of the heat exchanger are higher than the outlet and the inlet of the reactor, which are connected with the inlet pipeline and the outlet pipeline, the part of the outlet pipeline, which is positioned between the cooling water tank and the reactor, is provided with an isolation valve A, 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 reactor pressure value is reduced to a set value, the isolation valve A is opened to form a first heat exchange circulation loop. The heat removal can be realized by utilizing a passive mode, no external force is needed, and the heat removal device can still be used under the condition of losing power.
Description
Technical Field
The invention relates to the technical field of nuclear reactor safety, in particular to a primary side passive waste heat discharging system for a nuclear reactor.
Background
During the nuclear reaction, an emergency shutdown may occur for several reasons. The problem of deriving decay heat after reactor shutdown is a key problem related to the safety of the nuclear reactor, especially when a full ship power failure accident occurs in a marine reactor, the reactor loses an active waste heat discharge system, and if the reactor decay heat cannot be safely derived, serious accidents such as reactor melting and the like can be caused. Therefore, other related safety systems are needed to solve the problem of the export of the decay heat of the reactor core under the condition that the whole ship is powered off or other heat conduction paths lose working conditions. And compared with the land reactor, the space of the cabin of the marine reactor is limited, and how to utilize the limited space to achieve the maximum heat extraction is also a problem to be solved.
Disclosure of Invention
The invention aims to solve the technical problems of utilizing the limited space of a cabin to maximally remove heat and solving the problem of leading out the decay heat of a reactor core under the condition that the whole ship is powered off or other heat conduction paths lose work, and provides a primary side passive waste heat discharging system for a nuclear reactor, which solves the technical problem of leading out the decay heat after the nuclear reactor is shut down.
The invention is realized by the following technical scheme:
a primary side passive waste heat removal system for a nuclear reactor includes a reactor, a cooling water tank, an inlet pipe, an outlet pipe, 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 passes through the cooling water tank and is connected with the inlet of the heat exchanger, one end of the outlet pipeline is connected with the outlet of the heat exchanger and passes through the cooling water tank and is connected with the reactor, the inlet and the outlet of the heat exchanger are higher than the outlet and the inlet of the reactor, which are connected with the inlet pipeline and the outlet pipeline, the part of the outlet pipeline, which is positioned between the cooling water tank and the reactor, is provided with an isolation valve A, and the control unit is connected with the isolation valve A;
A pressure stabilizer is further arranged on the reactor heat pipeline between the inlet pipeline and the reactor, and is used for monitoring the reactor pressure value and transmitting the pressure signal to the control unit;
When the reactor is shut down and the reactor pressure value 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 part on the heat exchanger is of an arc structure.
Optionally, the inlet end of the heat exchanger is vertically higher than the outlet end thereof.
Optionally, the reactor and the cooling water tank are both located in the accommodating body, the inner side wall of the accommodating body is an arc-shaped curved surface, the cooling water tank is fixed on the inner side wall of the accommodating body, and the arc-shaped curved surface of the heat transfer part on the heat exchanger is matched with the arc-shaped curved surface of the accommodating body.
Optionally, the receiving body is a cabin.
Optionally, the accommodating body is located in the seawater, 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 joint of the cooling water tank and the accommodating body, a second heat exchange circulation loop is formed, seawater enters the cooling water tank through the inflow pore canals and flows out through the outflow pore canals, isolation valves B are arranged at the positions of each inflow pore canal and each outflow pore canal, each isolation valve B 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 reactor pressure value received by the control unit is reduced to a set value, the control unit controls the isolation valve B to be opened.
Optionally, one inflow duct and one outflow duct are respectively arranged.
Compared with the prior art, the invention has the following advantages and beneficial effects:
(1) The primary side passive waste heat discharging system for the nuclear reactor is provided with a cooling water tank and a heat exchanger, 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, a sufficient thermal driving pressure head is kept, once an accident condition such as emergency shutdown occurs, and the pressure of the reactor is monitored to be reduced to a certain value, the passive waste heat discharging system starts to operate, an isolation valve A is opened, a coolant in the reactor can enter the heat exchanger spontaneously by means of pressure driving by utilizing the thermal driving pressure head which is established in advance for heat exchange, and the coolant after heat exchange can return to the reactor by means of self gravity 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, and the subsequent circulating heat exchange process is carried out. Therefore, heat removal can be realized by utilizing an passive mode, external force is not needed, pump driving is not adopted, and the heat removal device can still be used under the condition of losing power.
(2) The primary side passive waste heat discharging system for the nuclear reactor provided by the embodiment of the invention is characterized in that the heat transfer part 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 tubular structure can be combined with the arc curved surface of the side wall of the cabin to the maximum extent, the limited space is fully utilized, and the maximum natural circulation potential difference is formed between the inlet end and the outlet end of the heat exchanger, so that the maximum natural circulation driving force is realized, the higher waste heat discharging capacity is ensured, and the normal operation of the first heat exchange circulation loop is ensured. And the arc-shaped 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 passive waste heat discharging system for the nuclear reactor is provided with an inflow duct and an outflow duct, wherein the inflow duct and the outflow duct are positioned between a joint of a cooling water tank and a containing body, the outflow duct is higher than the inflow duct, and an isolation valve B is arranged at the positions of the inflow duct and the outflow duct. After the passive waste heat discharging system is put into operation, seawater enters from the inflow pore canal at the lower part, flows out from the outflow pore canal at the upper part after heat exchange with the heat exchanger, and is driven by natural potential energy of the seawater to complete the seawater heat exchange cycle. The seawater is used as a final heat sink, and heat can be continuously introduced into the sea. And the height setting of the inlet end and the outlet end of the heat exchanger can provide good level difference for the circulating flow of seawater, and the natural circulating capacity of the seawater side is improved. Heat conduction can be performed under the passive condition without external force. And still be available in the event of a loss of power.
(4) The primary side passive waste heat discharging system for the nuclear reactor provided by the embodiment of the invention can effectively prevent instability of a seawater circulation loop from occurring under the condition that a cabin is not powered off, so that the waste heat discharging capability is reduced. And a voltage stabilizer is arranged to monitor the reactor pressure in real time, so that the timely feedback of the state is realized.
(5) The primary side passive waste heat discharging system for the nuclear reactor, provided by the embodiment of the invention, has compact overall structural 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 needed in the examples will be briefly described below, it being understood that the following drawings only illustrate some examples of the present invention and therefore should not be considered as limiting the scope, and that other related drawings may be obtained from these drawings without inventive effort for a person skilled in the art. In the drawings:
Fig. 1 is a schematic diagram of a primary passive residual heat removal system for a nuclear reactor according to an embodiment of the present invention.
In the drawings, the reference numerals and corresponding part names:
1-reactor, 2-heat exchanger, 3-cooling water tank, 4-isolation valve A, 5-isolation valve B, 6-cabin, 7-sea water, 8-stabilizer, 9-inlet pipeline, 10-outlet pipeline, 11-reactor heat pipeline.
Detailed Description
For the purpose of making apparent the objects, technical solutions and advantages of the present invention, the present invention will be further described in detail with reference to the following examples and the accompanying drawings, wherein the exemplary embodiments of the present invention and the descriptions thereof are for illustrating the present invention only and are not to be construed as limiting 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: no such specific details are necessary to practice the invention. In other instances, well-known structures, circuits, materials, or methods have not been described in detail in order not to obscure the invention.
Throughout the specification, references to "one embodiment," "an embodiment," "one example," or "an example" mean: a particular feature, structure, or characteristic described in connection with the embodiment or example is included within at least one embodiment of the invention. Thus, the appearances of the phrases "in one embodiment," "in an example," or "in 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. Moreover, those of ordinary skill in the art will appreciate that the illustrations provided herein are for illustrative purposes and that the illustrations are not necessarily drawn to scale. The term "and/or" as used herein 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", "high", "low", "inner", "outer", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, merely to facilitate description of the present invention and simplify description, and do not indicate or imply that the devices or elements referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the scope of the present invention.
Examples
A primary passive residual heat removal system for a nuclear reactor 1 comprises the 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 fixedly arranged in the cooling water tank 3, one end of the inlet pipeline 9 is fixedly connected with a corresponding outlet on the reactor 1, the other end of the inlet pipeline 9 penetrates through the cooling water tank 3 to be fixedly connected with an inlet of the heat exchanger 2, one end of the outlet pipeline 10 is fixedly connected with an outlet of the heat exchanger 2 and penetrates through the cooling water tank 3 to be fixedly connected with a corresponding inlet on the reactor 1, the outlet pipeline 10 is provided with an isolation valve A4 at a part positioned between the cooling water tank 3 and the reactor 1, the control unit is electrically connected or in communication with the isolation valve A4 and controls the operation of the isolation valve A4, a heat transfer part is fixedly arranged between the inlet and the outlet of the heat exchanger 2 and used for conducting and exchanging heat, and the heat transfer part on the heat exchanger 2 is of an arc-shaped structure, so that the heat conduction area is increased and the heat transfer efficiency is improved. A pressure regulator 8 is also provided on the reactor hot pipe 11 between the inlet pipe 9 and the reactor 1, the pressure regulator 8 being adapted to monitor the pressure value of the reactor 1 and to transmit a pressure value signal to the control unit. Corresponding to the reactor hot pipe 11, a reactor cold pipe 12 is provided in the reactor.
When the reactor 1 is stopped, the active waste heat discharging system of the first loop is put into operation firstly, the decay heat of the reactor core is led out, the pressure in the reactor is monitored in real time by the voltage stabilizer 8 and signals are transmitted to the control unit, the control unit compares the received pressure value with a set value, when the pressure value of the reactor 1 is reduced to the set value (3-4 Mpa), the passive waste heat discharging system is put into operation, 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, and thus a first heat exchange circulation loop is formed, the process can be carried out repeatedly 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 outlet of the heat exchanger 2 are both arranged higher than the outlet and inlet of the reactor 1, to which the inlet and outlet pipes 9, 10 are connected, and the inlet end of the heat exchanger 2 is arranged vertically higher than the outlet end thereof. Since the inlet line 9 is directly connected to the coolant system of the reactor 1, the heat exchanger 2 is in the same pressure state as the reactor 1 system, since the higher heat quantity during normal operation of the reactor 1 results in a higher temperature of the inlet line 9 directly connected thereto, and the water temperature of the inlet line 9 is higher than the water temperature of the outlet line 10, so that a sufficient thermal driving head is maintained between the reactor 1 and the inlet and outlet lines 9, 10 during normal operation of the reactor 1.
During normal operation of the reactor 1, due to the fact that the temperature of the cooling water tank 3, the outlet line 10 is lower than the temperature of the reactor 1, there is a pressure difference, and during operation of the reactor 1, a portion of the coolant in the reactor 1 enters the heat exchanger 2 via the inlet line 9 and is cooled in the heat exchanger 2. The inlet and the outlet of the heat exchanger 2 are higher than the outlet and the inlet of the reactor 1, which are connected with the inlet pipeline 9 and the outlet pipeline 10, even if the heat exchanger 2 is higher than the position of the reactor 1, enough heat driving pressure heads can be kept during normal operation of the reactor 1, and when the reactor 1 is in abnormal operation, even if accident working conditions occur, the coolant in the reactor 1 can enter the heat exchanger 2 by means of the heat driving pressure heads, and the coolant can return into the reactor 1 from the heat exchanger 2 by means of self gravity after heat exchange, so that the first heat extraction circulation loop can normally operate under the condition of power loss or accident working conditions.
In one or more embodiments, the heat transfer portion of the heat exchanger 2 is configured as an arc-shaped tubular structure, and both the reactor 1 and the coolant tank 3 are located in the accommodating body, which is the cabin 6. The inner side wall of the cabin 6 is an arc-shaped bending surface, the cooling water tank 3 is fixed on the inner side wall of the cabin 6, the arc-shaped bending surface of the heat transfer part on the heat exchanger 2 is matched with the arc-shaped bending surface of the cabin 6, and the heat transfer part of the heat exchanger 2 is made to be as close to the side wall of the cabin 6 as possible, so that the space is saved to the greatest extent, and the arc-shaped structure of the heat transfer part can be utilized to the greatest extent to increase the heat transfer efficiency.
In one or more embodiments, the cabin 6 is located in the seawater 7, a plurality of inflow channels and outflow channels through which the seawater 7 flows are further formed in the cabin 6, the inflow channels and the outflow channels are uniformly and correspondingly provided with isolation valves B5, the isolation valves B5 are connected with a control unit, the control unit controls the opening and closing of the isolation valves B5, any inflow channel is higher than each outflow channel in vertical height, and each inflow channel and each outflow channel are located between two connecting ends of the cooling water tank 3 and the cabin 6. Preferably, the inflow duct and the outflow duct are respectively arranged one, and the height of the outflow duct is positioned at the height of the inflow duct. After entering the cooling water tank 3 from the isolating valve of the inflow duct, 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 duct, thus circularly reciprocating to form a natural seawater circulation loop, namely a second heat transfer circulation loop. When the reactor is shut down and the reactor pressure value 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 controls the isolation valve B5 to be closed.
The working process of the primary side passive waste heat discharging 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 waste heat discharging system is in a standby state, the isolation valve A4 and the isolation valve B5 are 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, and the heat exchanger 2 is filled with coolant and is in the same pressure state as the reactor 1 system, so that a sufficient thermal driving pressure head is established and maintained during the normal operation of the reactor 1.
Under the accident condition, the reactor 1 protection system triggers an emergency shutdown, the kinetic energy waste heat discharge system on a loop firstly discharges heat, and when the pressure monitored in the voltage stabilizer 8 is reduced to 3-4 MPa, the control unit controls the isolation valve A4 and each isolation valve B5 to be opened, and the passive waste heat discharge system is put into operation to form two natural circulation loops: the first heat exchange circulation loop is the natural circulation of the coolant of the reactor 1 in the tube passes 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 returns to the reactor 1 by itself, and flows out into 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 entering pore canal and 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 exiting pore canal, so that the natural circulation loop of the seawater is formed.
The control unit may control the passive waste heat removal system via an electrical or communication connection, and the loss of power signal may be monitored by one or more other hardware devices according to a related procedure, signal converted, and retransmitted to the control unit, which will not be described in detail herein.
Those of ordinary skill in the art will appreciate that implementing all or part of the above facts and methods may be accomplished by a program to instruct related hardware, the program involved or the program may be stored in a computer readable storage medium, the program when executed comprising the steps of: the corresponding method steps are introduced at this time, and the storage medium may be a ROM/RAM, a magnetic disk, an optical disk, or the like.
The foregoing description of the embodiments has been provided for the purpose of illustrating the general principles of the invention, and is not meant to limit the scope of the invention, but to limit the invention to the particular embodiments, and any modifications, equivalents, improvements, etc. that fall within the spirit and principles of the invention are intended to be included within the scope of the invention.
Claims (6)
1. A primary passive residual heat removal system for a nuclear reactor, 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 passes 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 passes 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 outlet and inlet of the reactor (1) and the inlet pipeline (9) and the outlet pipeline (10), the part of the outlet pipeline (10) positioned between the cooling water tank (3) and the reactor (1) is provided with the isolation valve A (4), and the control unit is connected with the isolation valve A (4);
A pressure stabilizer (8) is further arranged on the 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 reactor pressure value received by the control unit is reduced to a set value, the control unit controls the isolation valve A (4) to be opened to form a first heat exchange circulation loop in which coolant enters the heat exchanger (2) through the inlet pipeline (9) and returns to the reactor (1) after heat exchange;
the reactor (1) and the cooling water tank (3) are both positioned in the accommodating body;
the accommodating body is positioned in the seawater (7), a plurality of inflow pore canals and outflow pore canals are also formed on the accommodating body, each inflow pore canal and each outflow pore canal are positioned between the joint of the cooling water tank (3) and the accommodating body, a second heat exchange circulation loop is formed, wherein the seawater (7) enters the cooling water tank (3) through the inflow pore canals and flows out through the outflow pore canals, isolation valves B (5) are arranged at the positions of each inflow pore canal and each outflow pore canal, 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 reactor pressure value received by the control unit is reduced to a set value, the control unit controls the isolation valve B (5) to be opened.
2. Primary passive residual heat removal system for nuclear reactors according to claim 1, characterized in that the heat transfer on the heat exchanger (2) is of arcuate configuration.
3. Primary passive residual heat removal system for nuclear reactors 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 passive residual heat removal system for a nuclear reactor according to claim 3, wherein the inner side wall of the containment body is curved, and the cooling water tank (3) is fixed to the inner side wall of the containment body, and the curved surface of the heat transfer portion of the heat exchanger (2) is fitted to the curved surface of the containment body.
5. Primary passive residual heat removal system for nuclear reactors according to claim 4, characterized in that the containment is a hold (6).
6. The primary passive residual heat removal system for a nuclear reactor of claim 1, wherein one inflow port and one outflow port are provided.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202111456131.7A CN114038591B (en) | 2021-12-01 | 2021-12-01 | Primary side passive waste heat discharging system for nuclear reactor |
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| CN202111456131.7A CN114038591B (en) | 2021-12-01 | 2021-12-01 | Primary side passive waste heat discharging system for nuclear reactor |
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| 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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| 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 |
| 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 |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN110739090B (en) * | 2019-10-14 | 2022-07-15 | 哈尔滨工程大学 | A passive waste heat removal system for heat pipe stacks using pressure vessel wall cooling |
| CN111554416A (en) * | 2020-05-29 | 2020-08-18 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Waste heat discharge system of heat pipe stack |
| CN113178272B (en) * | 2021-04-13 | 2023-05-23 | 西安交通大学 | Passive residual heat removal system of nuclear power unmanned submersible vehicle and working method |
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Patent Citations (2)
| 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 |
| 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 |
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