CN111477363B - Reactor core cooling system - Google Patents
Reactor core cooling system Download PDFInfo
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- CN111477363B CN111477363B CN201910067430.8A CN201910067430A CN111477363B CN 111477363 B CN111477363 B CN 111477363B CN 201910067430 A CN201910067430 A CN 201910067430A CN 111477363 B CN111477363 B CN 111477363B
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- water tank
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- 238000001816 cooling Methods 0.000 title claims abstract description 210
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 160
- 238000002955 isolation Methods 0.000 claims abstract description 55
- 239000007921 spray Substances 0.000 claims abstract description 31
- 238000004891 communication Methods 0.000 claims description 39
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 16
- 239000000126 substance Substances 0.000 claims description 9
- 230000001105 regulatory effect Effects 0.000 claims description 6
- 238000005507 spraying Methods 0.000 description 27
- 239000002826 coolant Substances 0.000 description 6
- 238000007599 discharging Methods 0.000 description 5
- 239000002918 waste heat Substances 0.000 description 4
- 239000000498 cooling water Substances 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000000746 purification Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000284 extract Substances 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
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
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
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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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
本发明提供一种反应堆堆芯冷却系统，包括：喷淋装置和N根冷却管；每个冷却管的第一端均与所述反应堆压力容器的热出水口连通，每个冷却管均沿着各自的第一端至第二端的方向上依次连接有冷却管隔离阀、泵和热交换器，其中，所述N为大于或者等于2的整数；每个冷却管的第二端均通过至少一个压力容器隔离阀与所述反应堆压力容器的进水口连通；每个冷却管的第二端均通过至少一个喷淋装置隔离阀与所述喷淋装置连接。本实施例提供的反应堆堆芯冷却系统可以同时具备安全壳喷淋功能和反应堆余热排出功能，从而精简了冷却设备，降低了成本。
The present invention provides a reactor core cooling system, comprising: a spray device and N cooling pipes; the first end of each cooling pipe is connected to the hot water outlet of the reactor pressure vessel, and each cooling pipe is sequentially connected to a cooling pipe isolation valve, a pump and a heat exchanger along the direction from the first end to the second end, wherein N is an integer greater than or equal to 2; the second end of each cooling pipe is connected to the water inlet of the reactor pressure vessel through at least one pressure vessel isolation valve; the second end of each cooling pipe is connected to the spray device through at least one spray device isolation valve. The reactor core cooling system provided in this embodiment can have both the containment spray function and the reactor residual heat discharge function, thereby streamlining the cooling equipment and reducing costs.
Description
Technical Field
The invention relates to the technical field of nuclear power, in particular to a reactor core cooling system.
Background
Along with the progress of science and technology, the variety of electric energy adopted in life of people is also more and more abundant, and nuclear power generated by a nuclear power station occupies an increasingly important position in life of people. In practical use, a plurality of sets of cooling devices for cooling the reactor and the containment vessel are generally provided, but since each set of cooling devices can only realize a single cooling function, for example: each set of cooling equipment can realize the spraying function to the containment, or realize the function of discharging the reactor waste heat to lead to cooling equipment comparatively redundant, the cost is higher.
Disclosure of Invention
The embodiment of the invention aims to provide a reactor core cooling system, which solves the problems of redundancy of cooling equipment and high cost.
In order to achieve the above object, an embodiment of the present invention provides a reactor core cooling system, which is applied to a nuclear power plant including a reactor pressure vessel, a spent fuel pool cooling system, and a chemical and volumetric control system, the reactor core cooling system comprising: the spray device and the N cooling pipes;
The first end of each cooling pipe is communicated with a hot water outlet of the reactor pressure vessel, and each cooling pipe is sequentially connected with a cooling pipe isolation valve, a pump and a heat exchanger along the direction from the respective first end to the second end, wherein N is an integer greater than or equal to 2;
the second end of each cooling pipe is communicated with a water inlet of the reactor pressure vessel through at least one pressure vessel isolation valve;
The second end of each cooling pipe is connected with the spraying device through at least one spraying device isolation valve.
Optionally, the nuclear power plant further comprises a material-changing water tank, and each cooling pipe is provided with a first communication port between the respective first end and the pump;
The reactor core cooling system further comprises a water taking pipeline of the refueling water tank, the refueling water tank is communicated with each first communication port through a water taking pipeline of the refueling water tank, and at least one isolation valve of the refueling water tank is connected in each water taking pipeline of the refueling water tank.
Optionally, the water intake pipeline of each refueling water tank is communicated with the water outlet of the refueling water tank through a filter.
Optionally, the reactor core cooling system further comprises at least one refueling water return line, and the second end of each cooling pipe is communicated with the refueling water tank through one refueling water return line.
Optionally, the pump and the heat exchanger in each cooling tube are arranged outside the containment of the nuclear power plant.
Optionally, each cooling tube is connected with a check valve between the respective pump and heat exchanger.
Optionally, the second end of each cooling pipe is connected to the spray device through at least two spray device isolation valves, and the at least two spray device isolation valves are connected in parallel with each other.
Optionally, each cooling tube further has a second communication port and a third communication port therein, each second communication port being located between the first end of each cooling tube and the pump in each cooling tube, each third communication port being located between the heat exchanger in each cooling tube and the second end of each cooling tube;
The reactor core cooling system further comprises at least one flow pipeline, the first end of each flow pipeline is communicated with the water intake pipeline of the spent fuel pool cooling system through a second communication port in one cooling pipe, and the second end of each flow pipeline is communicated with the water return pipeline of the spent fuel pool cooling system through a third communication port in the corresponding cooling pipe.
Optionally, the reactor core cooling system further comprises at least one first header and/or at least one second header;
Each cooling pipe is provided with a fourth communication port between the respective pump and the heat exchanger;
communicating with a drain line of the chemical and volumetric system at a fourth communication port of each cooling tube;
Each first header is communicated with the fourth communication ports of two adjacent cooling pipes respectively, and each second header is communicated with the third communication ports of two adjacent cooling pipes respectively.
Optionally, each cooling tube is connected with a flow regulating valve between the respective heat exchanger and the third communication port.
Optionally, each cooling tube is connected with an overpressure protection relief valve between the respective first end and the pump.
One of the above technical solutions has the following advantages or beneficial effects:
the reactor core cooling system provided by the embodiment of the invention comprises: the spray device and the N cooling pipes; the first end of each cooling pipe is communicated with a hot water outlet of the reactor pressure vessel, and each cooling pipe is sequentially connected with a cooling pipe isolation valve, a pump and a heat exchanger along the direction from the respective first end to the second end, wherein N is an integer greater than or equal to 2; the second end of each cooling pipe is communicated with a water inlet of the reactor pressure vessel through at least one pressure vessel isolation valve; the second end of each cooling pipe is connected with the spraying device through at least one spraying device isolation valve. Therefore, the reactor core cooling system provided by the embodiment can have the containment spraying function and the reactor waste heat discharging function at the same time, so that cooling equipment is simplified, and the cost is reduced.
Drawings
Fig. 1 is a schematic structural diagram of a reactor core cooling system according to the present invention.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and fully with reference to the accompanying drawings, in which it is evident that the embodiments described are some, but not all embodiments of the invention. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
As shown in fig. 1, an embodiment of the present invention provides a reactor core cooling system applied to a nuclear power plant including a reactor pressure vessel 1, a spent fuel pool cooling system 2, and a chemical and volumetric control system 3, the reactor core cooling system including: a spraying device 4 and N cooling pipes 5;
The first end of each cooling pipe 5 is communicated with the hot water outlet of the reactor pressure vessel 1, and each cooling pipe 5 is sequentially connected with a cooling pipe isolation valve 6, a pump 7 and a heat exchanger 8 along the direction from the respective first end to the second end, wherein N is an integer greater than or equal to 2;
the second end of each cooling pipe 5 is communicated with the water inlet of the reactor pressure vessel 1 through at least one pressure vessel isolation valve 9;
the second end of each cooling pipe 5 is connected to the spraying device 4 via at least one spraying device isolation valve 10.
The working principle of this embodiment can be seen as follows:
The first end of each cooling pipe 5 extracts hot water from the water inlet of the reactor pressure vessel 1 and passes the hot water through the cooling pipe isolation valve 6, the pump 7 and the heat exchanger 8 in each cooling pipe 5 in this order, and cooling water is taken in the heat exchanger 8 through a pipeline, heat exchange is performed between the hot water and the cooling water in the heat exchanger 8, and after the temperature of the hot water is lowered, the cooled hot water is injected into the reactor pressure vessel 1 through the second end of the cooling pipe 5. In this way, heat in the reactor pressure vessel 1 can be removed better. It should be noted that, the cooling pipe 5 can discharge the heat in the reactor pressure vessel 1 through the above steps, both under normal operation and under design reference accident.
In addition, the water after heat exchange in the heat exchanger 8 is directly injected into the reactor pressure vessel 1, not into the cold-stage pipeline of the reactor pressure vessel 1, so that the phenomenon that the water cannot be injected into the reactor pressure vessel 1 due to the rupture of the cold-stage pipeline can be avoided, and the safety is further improved.
In addition, when a design reference accident such as a break of a main steam pipe or a large break in a main pipe of a reactor coolant system in a nuclear power plant occurs, the pressure in the containment 11 rapidly rises, and at this time, the sprinkler isolation valve 10 may be opened, and when the pressure reaches a trigger point of the sprinkler 4, the sprinkler 4 starts to spray cold water to reduce the pressure in the containment 11 to a safe value.
In this way, the reactor core cooling system provided by the embodiment not only can timely discharge heat in the reactor pressure vessel 1, but also can realize a spraying function in the containment 11 so as to reduce the pressure in the containment 11, thereby simplifying cooling equipment and reducing cost.
In addition, alternatively, the pump 7 and the heat exchanger 8 in each cooling pipe 5 may be disposed outside the containment 11 of the nuclear power plant, and the remaining components of the entire reactor core cooling system except for the pump 7 and the heat exchanger 8 may be disposed inside the containment 11. In this way, the volume of the containment 11 can be made smaller, thereby further reducing the cost of use. Of course, the installation positions of the above-described members are not particularly limited herein. For example: all components of the reactor core cooling system may be disposed within the containment 11.
It should be noted that, when the cooling pipe 5 passes through the containment vessel 11, the isolation valve 1101 is disposed on the cooling pipe 5 located inside the containment vessel 11 and outside the containment vessel 11, and the isolation valve 1101 needs to be disposed close to the shell of the containment vessel 11.
Wherein the hot water outlet of the reactor pressure vessel 1 may also be referred to as the reactor coolant loop hot leg.
The specific type of the spraying device 4 is not limited herein, for example: the spraying device 4 may be in the form of a spray collar. And a check valve may also be provided between the sprinkler 4 and the sprinkler isolation valve 10.
The reactor core cooling system provided by the embodiment of the invention comprises: the spray device and the N cooling pipes; the first end of each cooling pipe is communicated with a hot water outlet of the reactor pressure vessel, and each cooling pipe is sequentially connected with a cooling pipe isolation valve, a pump and a heat exchanger along the direction from the respective first end to the second end, wherein N is an integer greater than or equal to 2; the second end of each cooling pipe is communicated with a water inlet of the reactor pressure vessel through at least one pressure vessel isolation valve; the second end of each cooling pipe is connected with the spraying device through at least one spraying device isolation valve. Therefore, the reactor core cooling system provided by the embodiment can have the containment spraying function and the residual heat discharging function of the reactor, so that cooling equipment is simplified, and the cost is reduced.
Optionally, the plant further comprises a refueling water tank 12, each cooling tube 5 being provided with a first communication port between a respective first end and the pump 7;
As shown in fig. 1, the reactor core cooling system further includes a water-tank water intake pipe 1201, and the water-tank 12 is communicated with each first communication port through a water-tank water intake pipe 1201, and at least one water-tank isolation valve 1202 is connected to each water-tank water intake pipe 1201.
Wherein the spraying device 4 can take water from the water tank 12 and then spray the water to reduce the pressure of the containment vessel 11. It should be noted that, the water taken from the refueling water tank 12 may sequentially pass through the pump 7 and the heat exchanger 8 and then reach the spraying device 4, so that the heat exchange of the water may be performed through the heat exchanger 8 to reduce the temperature of the water, so that the spraying effect of the spraying device 4 is better.
Preferably, two tank isolation valves 1202 are connected to each tank water intake line 1201, and the tank isolation valves 1202 may be electric valves, so that the tank isolation valves 1202 are opened or closed more conveniently.
It should be noted that the refueling water tank 12 may be placed in the containment 11.
In the embodiment of the invention, the material changing water tank is arranged, so that the water taking of the spraying device is more convenient during spraying.
Optionally, as shown in fig. 1, each of the water supply lines 1201 of the refueling water storage tank is communicated with the water outlet of the refueling water storage tank 12 through a filter 1203.
The specific type of the filter 1203 is not limited herein. For example: the filter 1203 may be a screen or a sheet of material with holes, etc.
In the embodiment of the invention, the water taking pipeline of each refueling water tank is communicated with the water outlet of the refueling water tank through the filter, so that the phenomenon that impurities with larger volume in the refueling water tank enter the water taking pipeline of the refueling water tank to further block the water taking pipeline of the refueling water tank can be reduced.
Optionally, as shown in FIG. 1, the reactor core cooling system further includes at least one refueling water return line 1204, and the second end of each cooling tube 5 communicates with the refueling water tank 12 through one refueling water return line 1204.
When a design reference accident occurs, the pressure in the containment 11 rises rapidly, so that the water temperature in the water tank 12 also rises rapidly, and at this time, the water in the water tank 12 can pass through the water intake pipe 1201 of the water tank, the pump 7 and the heat exchanger 8 in sequence, and heat exchange is performed on the water in the heat exchanger 8, so as to reduce the temperature of the water, and the water with reduced temperature returns to the water tank 12 through the water return pipe 1204 of the water tank, so that the temperature of the water in the water tank 12 is reduced, and the water tank 12 is cooled.
In addition, the refueling water intake line 1201 and the refueling water return line 1204 may both be provided in the containment 11, thereby reducing the number of components penetrating the containment 11, making the surface of the containment 11 more complete.
In addition, an isolation valve may be disposed between the second end of the cooling pipe 5 and the return line 1204 of the refueling water tank, and the isolation valve is preferably an electric isolation valve.
In the embodiment of the invention, the reactor core cooling system further comprises at least one water return pipeline of the refueling water tank, and the second end of each cooling pipe is communicated with the refueling water tank through one water return pipeline of the refueling water tank, so that the aim of reducing the water temperature in the refueling water tank can be fulfilled, and the aim of cooling the refueling water tank is fulfilled.
Optionally, as shown in fig. 1, each cooling tube 5 is connected with a check valve 13 between the respective pump 7 and heat exchanger 8.
The check valve 13 is connected between the pump 7 and the heat exchanger 8, and the check valve 13 has a one-way circulation characteristic, so that water can only flow from the pump 7 to the heat exchanger 8, water is prevented from flowing from the heat exchanger 8 to the pump 7, and especially, hot water in the heat exchanger 8 is prevented from flowing back to the pump 7 and then flowing back to the reload water tank 12, and damage to the reload water tank 12 is avoided.
In the embodiment of the invention, a check valve is connected between the pump and the heat exchanger, so that water in the heat exchanger is prevented from flowing back into the pump.
Alternatively, as shown in fig. 1, the second end of each cooling pipe 5 is connected to the spraying device 4 through at least two spraying device isolation valves 10, and the at least two spraying device isolation valves 10 are connected in parallel to each other.
Wherein preferably the number of sprinkler isolation valves 10 is two.
In the embodiment of the invention, the spray device isolation valves are connected in parallel, so that compared with the mode of connecting the spray device isolation valves in series, the spray device isolation valves can avoid the phenomenon that the whole spray device cannot work normally when one spray device isolation valve fails, thereby improving the stability of the spray function of the whole reactor core cooling system.
Optionally, as shown in fig. 1, each cooling tube 5 further has a second communication port and a third communication port therein, each second communication port being located between the first end of each cooling tube 5 and the pump 7 in each cooling tube 5, each third communication port being located between the heat exchanger 8 in each cooling tube 5 and the second end of each cooling tube 5;
The reactor core cooling system further includes at least one flow line 14, a first end of each flow line 14 is in communication with the water intake line 201 of the spent fuel pool cooling system 2 through a second communication port in one cooling pipe 5, and a second end of each flow line 14 is in communication with the water return line 202 of the spent fuel pool cooling system 2 through a third communication port in a corresponding cooling pipe 5.
Wherein the second communication port communicating with the first end of the flow line 14 and the third communication port communicating with the second end of the flow line 14 are both located in the same cooling tube 5.
Wherein, optionally, as shown in FIG. 1, the reactor core cooling system further comprises at least one first header 1501 and/or at least one second header 1502;
each cooling tube 5 is provided with a fourth communication port between the respective pump 7 and heat exchanger 8;
a fourth communication port of each cooling pipe 5 is communicated with a drain line of the chemical and volumetric system 3;
Each first header 1501 communicates with the fourth communication ports of two adjacent cooling pipes 5, respectively, and each second header 1502 communicates with the third communication ports of two adjacent cooling pipes 5, respectively.
Wherein, two adjacent cooling pipes 5 can be communicated through the first header 1501 and the second header 1502, and when part of components in one cooling pipe 5 fail, the two adjacent cooling pipes 5 can be communicated through the first header 1501 and the second header 1502, so that the cooling pipes 5 can work normally.
For example: when a first end of a certain cooling pipe 5 is disconnected from the hot water outlet of the reactor pressure vessel 1, the cooling pipe 5 cannot take water from the reactor pressure vessel 1. But the cooling tubes 5 may be fed from the reactor pressure vessel 1 through the first header 1501 from the first end of the adjacent cooling tube 5, thereby allowing for better stability of the overall reactor core cooling system.
The first manifold 1501 and the second manifold 1502 may be provided with a plurality of isolation valves, respectively, and the isolation valves may be preferably electrically operated isolation valves.
In the embodiment of the invention, the first header pipe and the second header pipe can enable two adjacent cooling pipes to be communicated with each other, and when part of components in one cooling pipe fail, the first header pipe and the second header pipe can also act, so that the working stability of each cooling pipe is improved.
When the nuclear power plant is in normal operation, the pump 7 and the first end of the cooling pipe 5, and the heat exchanger 8 and the second end of the cooling pipe 5 may be in an off state, that is, the cooling pipe isolation valve 6, the pump 7 and the pressure vessel isolation valve 9 are all in an off state, and a part of the cooling pipe between the pump 7 and the heat exchanger 8 may be in a communication state, then water may be taken from the spent fuel pool cooling system through the water intake pipeline 201 of the spent fuel pool cooling system 2 at this time, so that the part of the cooling pipe between the pump 7 and the heat exchanger 8, and the flow pipeline 14 may be filled with water.
Under the reactor shutdown condition, the reactor core cooling system can play a role in discharging the residual heat of the reactor, namely, the cooling pipe isolation valve 6 is in an open state, so that hot water can be extracted from the reactor pressure vessel 1 through the first end of the cooling pipe 5, and the hot water can flow into the water return pipeline 202 of the spent fuel pool cooling system 2 and the drain pipeline of the chemical and volumetric control system 3 through the flow pipeline 14, so that the function of 'heating pipes' of the cooling pipe 5 is completed. Of course, when the pump 7 is just started, the water flow rate of the pump 7 is smaller, and the hot water pumped from the reactor pressure vessel 1 through the first end of the cooling pipe 5 can be divided into three parts, wherein one part flows into the heat exchanger 8 through the pump 7, one part flows into the drain line of the chemical and volume control system 3, and the other part flows into the return line 202 of the spent fuel pool cooling system 2 through the flow line 14, so that the function of 'heating pipe' of the cooling pipe 5 is continuously completed. Of course, when the temperature of the cooling pipe 5 increases, the flow rate of water passing through the pump 7 can be increased, and the flow rate of water passing through the flow line 14 at this time is correspondingly decreased.
When a main steam pipe break or a design reference accident such as a large break occurs in a main pipe of a reactor coolant system in a nuclear power plant, the reactor core cooling system can exert a spraying function at this time, that is, the pressure in the containment 11 is rapidly increased, and at this time, the spray device isolation valve 10 and the refueling water tank isolation valve 1202 can be opened, and the spray device 4 sprays to reduce the pressure and temperature in the containment 11.
It should be noted that the reactor shutdown condition includes normal shutdown and shutdown after design reference accident.
When the pressure and temperature in the containment 11 drop to safe values, the reactor core cooling system can perform the reactor waste heat discharging function at this time, namely, the spray device isolation valve 10 and the refueling water tank isolation valve 1202 can be closed, the cooling pipe isolation valve 6 and the pressure vessel isolation valve 9 are opened, so that the cooling pipe 5 can take hot water from the hot water outlet of the reactor pressure vessel 1 through the first end, and after the hot water is cooled through the heat exchanger 8, the cooled water is returned to the reactor pressure vessel 1, thereby achieving the effect of cooling the reactor pressure vessel 1. In this way, the reactor core cooling system reduces damage to equipment in the containment 11 when the reactor core cooling system is in the containment spraying function for a long period of time by switching between the containment spraying function and the reactor waste heat removal function.
In addition, it should be noted that a refueling water tank purifying line 203 may be connected to the water intake line 201 of the spent fuel pool cooling system 2, one end of the refueling water tank purifying line 203 is communicated with the refueling water tank 12 through the cooling pipe 5 and the refueling water tank water intake line 1202, and the other end of the refueling water tank purifying line 203 is communicated with the refueling water tank purifying line in the spent fuel pool cooling system 2, so as to achieve the purpose of purifying water in the refueling water tank 12. Namely, the water in the refueling water storage tank 12 can be replaced by forming a loop through the refueling water intake pipe 1202, the cooling pipe 5, the refueling water purification pipe 203 and the refueling water purification pipe in the spent fuel pool cooling system 2.
In the embodiment of the invention, the flow pipeline is arranged, so that the functions of the reactor core cooling system are more diversified and more stable.
Alternatively, as shown in fig. 1, each cooling pipe 5 is connected with a flow regulating valve 16 between the respective heat exchanger 8 and the third communication port.
Wherein when the flow regulating valve 16 is in operation, excess water in the cooling pipe 5 can flow from the flow line 14 to act as a shunt.
In addition, a communicating pipe 1503 may be provided that communicates with the first header 1501 and the second header 1502, respectively, and a communicating port may be provided in the communicating pipe 1503 for communicating with a drain line of the chemical and volumetric control system 3. Note that, the bypass flow rate adjusting valve 1504 may be further provided to the communicating pipe 1503, so that the flow rate adjusting valve 16, the bypass flow rate adjusting valve 1504, and the flow line 14 may cooperate with each other to adjust the flow rate of water passing through the pump 7 and the heat exchanger 8 in each cooling pipe 5, and the flow rate of water passing through the pump 7 and the heat exchanger 8 in each cooling pipe 5 may be made more stable and uniform.
In the embodiment of the invention, the flow regulating valve is connected between the heat exchanger and the third communication port, so that the flow of water in each cooling pipe can be conveniently regulated.
Optionally, as shown in fig. 1, each cooling tube 5 is connected with an overpressure protection safety valve 17 between the respective first end and the pump 7.
When the reactor coolant system in the nuclear power plant is in a cold overpressure condition, for example, due to the false start of the reactor coolant pump, the overpressure protection safety valve 17 is opened to prevent the system pressure from exceeding the design pressure, so as to protect the reactor coolant system and the reactor core cooling system in the embodiment from being damaged.
In the embodiment of the invention, each cooling pipe is connected with the overpressure protection safety valve between the respective first end and the pump, so that the safety performance of the reactor core cooling system can be improved.
The foregoing is merely illustrative of the present invention, and the present invention is not limited thereto, and any person skilled in the art will readily recognize that variations or substitutions are within the scope of the present invention. Therefore, the protection scope of the invention is subject to the protection scope of the claims.
Claims (9)
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| CN201910067430.8A CN111477363B (en) | 2019-01-24 | 2019-01-24 | Reactor core cooling system |
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| CN201910067430.8A CN111477363B (en) | 2019-01-24 | 2019-01-24 | Reactor core cooling system |
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| CN102426864B (en) * | 2011-12-12 | 2014-03-26 | 曾祥炜 | Passive emergency cooling system for severe accident in reactor |
| CN204834063U (en) * | 2015-06-29 | 2015-12-02 | 中国原子能科学研究院 | Active waste heat discharge heat exchanger test device of non - |
| JP6773463B2 (en) * | 2016-06-20 | 2020-10-21 | 株式会社東芝 | Chemical decontamination method for pressurized water nuclear power plant |
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|---|---|---|---|---|
| JPH1010271A (en) * | 1996-06-25 | 1998-01-16 | Toshiba Corp | Nuclear reactor pressure vessel cooler |
| CN104217773A (en) * | 2014-07-30 | 2014-12-17 | 中国核电工程有限公司 | Nuclear power plant steel safe containment vessel heat-conductive device |
| CN209591541U (en) * | 2019-01-24 | 2019-11-05 | 华龙国际核电技术有限公司 | A kind of reactor core cooling system |
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| CN111477363A (en) | 2020-07-31 |
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