CN215911200U - Waste heat discharge system and nuclear power system - Google Patents
Waste heat discharge system and nuclear power system Download PDFInfo
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- CN215911200U CN215911200U CN202121529424.9U CN202121529424U CN215911200U CN 215911200 U CN215911200 U CN 215911200U CN 202121529424 U CN202121529424 U CN 202121529424U CN 215911200 U CN215911200 U CN 215911200U
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Abstract
The utility model provides a waste heat discharge system and a nuclear power system, comprising: the preheating unit is connected between an inlet and an outlet of the waste heat discharge unit and used for forming circulation with the waste heat discharge unit, coolant in the waste heat discharge unit is pumped into the preheating unit to be heated and then is conveyed back to the waste heat discharge unit, the waste heat discharge unit is connected between a hot section and a cold section of a reactor coolant system and used for cooling the reactor coolant system to a first set value, and the coolant in the waste heat discharge unit is heated to a second set value and then forms circulation with the reactor coolant system, and the coolant in the hot section is pumped into the cooling unit to be cooled and then is conveyed to the cold section. Therefore, the system can start to work when the reactor leaves a hot shutdown condition, and completes preheating work after a loop meets the access condition of the waste heat discharge system, so that overhaul time is not occupied, shutdown time of the power plant is shortened, and economy of the power plant is improved.
Description
Technical Field
The utility model particularly relates to a waste heat discharge system and a nuclear power system.
Background
The waste heat discharge system is in a state of normal temperature and normal pressure before being put into operation to cool the reactor cooling system. The waste heat discharge system is directly connected to a reactor coolant system, and can lead to the fact that a medium at normal temperature in the pipeline is directly injected into a reactor coolant pipeline and a pressure container, so that the thermal stress and thermal shock of a loop are caused, accumulated fatigue can cause the risk of failure of the pipeline and the container to increase, and service life equipment is shortened. Therefore, the second and third generation nuclear power plants running in China need to be preheated before the waste heat discharge system is put into operation.
The preheating process comprises the steps of opening the isolation between a reactor coolant system and a waste heat discharge system, opening the isolation between a chemical and volume control system (RCV) and the waste heat discharge system, controlling the downward discharge flow from the reactor coolant system to the RCV system through the waste heat discharge system by a valve of the RCV, starting a waste heat discharge pump, circulating to uniform media, and controlling the preheating temperature rise rate through a bypass pipeline of a heat exchanger of the waste heat discharge system. The medium of the system is heated to about 120 ℃, and then a return pipeline of the residual heat discharge and reactor coolant system can be communicated, and the residual heat discharge system is connected to the shutdown and temperature reduction process of the reactor.
According to the related calculation report, the power of the power plant runs for one day, and the income can reach 1200 ten thousand. According to the operation experience feedback of the traditional 310-type reactor and other domestic three-generation nuclear reactor types, the preheating of the waste heat discharge system is the main line time in the process of overhaul and material change, and the preheating needs 4-6 hours to be completed. Therefore, there is a need for an improved residual heat removal system to reduce overhaul periods and increase unit availability and core competitiveness.
SUMMERY OF THE UTILITY MODEL
The utility model aims to solve the technical problem of providing a waste heat discharge system which does not occupy the operation of a main line during preheating, compresses the shutdown time of a power plant and improves the economical efficiency of the power plant aiming at the defects in the prior art, and also correspondingly provides a nuclear power system with the waste heat discharge system.
The technical scheme adopted for solving the technical problem of the utility model is as follows:
the utility model provides a waste heat discharge system, comprising: a waste heat discharge unit and a preheating unit,
the preheating unit is connected between the inlet and the outlet of the residual heat discharging unit and used for forming circulation with the residual heat discharging unit when the residual heat discharging unit is disconnected with the reactor coolant system, and pumping the coolant in the residual heat discharging unit into the preheating unit for heating and then conveying the coolant back to the residual heat discharging unit,
the waste heat discharge unit is connected between a hot section and a cold section of the reactor coolant system and used for cooling the reactor coolant system to a first set value, the coolant in the waste heat discharge unit is disconnected with the preheating unit and forms circulation with the reactor coolant system after being heated to a second set value, the coolant in the hot section is pumped into the waste heat discharge unit for cooling, and then the coolant is conveyed to the cold section, and the first set value is larger than the second set value.
Optionally, the waste heat discharge unit comprises a waste heat discharge pipe, a first valve bank, a cooling pump, a heat exchanger and a second valve bank, the waste heat discharge pipe is connected between a hot section of the reactor coolant system and a cold section of the reactor coolant system, the first valve bank, the cooling pump, the heat exchanger and the second valve bank are sequentially arranged on the waste heat discharge pipe, the coolant in the hot section is pumped into the heat exchanger through the cooling pump for cooling and then enters the cold section,
the preheating unit comprises a preheating pipe, a heating structure, a heating pump and a third valve group, the preheating pipe is connected between a first communicating port and a second communicating port of the waste heat discharging pipe, the first communicating port is the second valve group and the position between the heat exchangers, the second communicating port is the position between the first valve group and the cooling pump, the heating structure, the heating pump and the third valve group are arranged on the preheating pipe, and a coolant in the waste heat discharging unit is pumped into the heating structure through the heating pump to be heated and then returns to the waste heat discharging unit.
Optionally, the waste heat discharge pipe further comprises a small flow pipe, the small flow pipe is connected between the first communicating port and the second communicating port of the waste heat discharge pipe, and the inner diameter of the small flow pipe is smaller than that of the waste heat discharge pipe.
Optionally, the waste heat discharge pipe comprises a first bus section, a suction section, a second bus section, a cooling pump section, a third bus section, a heat exchanger section, a fourth bus section and a return section which are communicated in sequence along the flow direction of the coolant,
the first parent segment is communicated with the hot segment of the reactor coolant system, the return segment is communicated with the cold segment of the reactor coolant system,
the cooling pump is arranged on the cooling pump section, the heat exchanger is arranged on the heat exchanger section,
the waste heat discharge pipe also comprises a bypass pipe section, and the bypass pipe section is connected between the third female section and the fourth female section.
Optionally, the first valve block comprises a first intake isolation valve and a second intake isolation valve,
the first suction isolation valves are positioned on the suction sections, the suction sections are positioned in the containment, the number of the suction sections is two, each suction section is provided with two first suction isolation valves, a pressure locking device is arranged between the two first suction isolation valves of each suction section,
the second suction isolation valve is positioned on the second female section, and the second female section is positioned outside the containment.
The second valve bank includes a first return isolation valve, a first check valve, a return check valve, and a second return isolation valve,
the two return sections are provided, one return section is connected with the cold section of the first loop of the reactor coolant system, the other return section is connected with the cold section of the third loop of the reactor coolant system, each return section is provided with a first return isolating valve, a first check valve is arranged at the position, between the cold section and the first return isolating valve, of each return section,
the return check valve and the second return isolation valve are both located on the fourth female section, the fourth female section penetrates through the containment, the return check valve is located in the containment, and the second return isolation valve is located outside the containment.
Optionally, a plurality of heat exchangers are arranged, a plurality of heat exchanger sections are correspondingly arranged, each heat exchanger section is provided with an adjusting valve, and the bypass pipe section is also provided with an adjusting valve;
the cooling pump is equipped with a plurality ofly, and the cooling pump section is equipped with many correspondingly, all is equipped with the second check valve on the every cooling pump section.
Optionally, a connecting tube is included that connects between the bypass section and the chemical and volumetric control system.
Optionally, the safety device further comprises a suction pipe, one end of the suction pipe is communicated with the part, located in the safety shell, of the second female section, and a safety valve is arranged at the other end of the suction pipe.
Optionally, the third valve bank comprises a first preheating regulating valve and a second preheating regulating valve, the first preheating regulating valve is arranged between the first communicating port of the waste heat discharging pipe and the heating structure, and the second preheating regulating valve is arranged between the heating pump and the second communicating port.
The utility model also provides a nuclear power system which comprises a reactor coolant system and the waste heat discharge system.
According to the utility model, the self-heating function of the waste heat discharge system can be completed by arranging the independent preheating unit, so that the system does not need other systems to participate in preheating before the traditional waste heat discharge system is put into operation, can start to work when the reactor leaves a thermal shutdown condition, and completes preheating work when a loop meets the access condition of the waste heat discharge system, thereby not occupying overhaul time, compressing shutdown time of a power plant, and improving the unit availability and core competitiveness.
Drawings
Fig. 1 is a schematic structural diagram of a waste heat removal system provided in embodiment 1 of the present invention.
Detailed Description
The technical solutions in the present invention will be described clearly and completely with reference to the accompanying drawings, and it should be understood that the described embodiments are only some embodiments, but not all embodiments, of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the scope of the present invention.
In the description of the present invention, it should be noted that the indication of orientation or positional relationship, such as "on" or the like, is based on the orientation or positional relationship shown in the drawings, and is only for convenience and simplicity of description, and does not indicate or imply that the device or element referred to must be provided with a specific orientation, constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention.
In the description of the present invention, the terms "first" and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it is to be noted that, unless otherwise explicitly specified or limited, the terms "connected," "disposed," "mounted," "fixed," and the like are to be construed broadly, e.g., as being fixedly or removably connected, or integrally connected; either directly or indirectly through intervening media, or may be interconnected between two elements. The specific meaning of the above terms in the present invention can be understood in specific cases for those skilled in the art.
The utility model provides a waste heat discharge system, comprising: a waste heat discharge unit and a preheating unit,
the preheating unit is connected between the inlet and the outlet of the residual heat discharging unit and used for forming circulation with the residual heat discharging unit when the residual heat discharging unit is disconnected with the reactor coolant system, and pumping the coolant in the residual heat discharging unit into the preheating unit for heating and then conveying the coolant back to the residual heat discharging unit,
the waste heat discharge unit is connected between a hot section and a cold section of the reactor coolant system and used for cooling the reactor coolant system to a first set value, the coolant in the waste heat discharge unit is disconnected with the preheating unit and forms circulation with the reactor coolant system after being heated to a second set value, the coolant in the hot section is pumped into the waste heat discharge unit for cooling, and then the coolant is conveyed to the cold section, and the first set value is larger than the second set value.
The utility model also provides a nuclear power system which comprises a reactor coolant system and the waste heat discharge system.
Example 1:
as shown in fig. 1, the present embodiment provides a waste heat removal system, including: a waste heat discharge unit and a preheating unit,
the preheating unit is connected between the inlet and the outlet of the residual heat discharging unit and used for forming circulation with the residual heat discharging unit when the residual heat discharging unit is disconnected with the reactor coolant system, and pumping the coolant in the residual heat discharging unit into the preheating unit for heating and then returning the coolant to the residual heat discharging unit,
the waste heat discharge unit is connected between a hot section and a cold section of the reactor coolant system and used for cooling the reactor coolant system to a first set value, the coolant in the waste heat discharge unit is disconnected with the preheating unit and forms circulation with the reactor coolant system after being heated to a second set value, the coolant in the hot section is pumped into the waste heat discharge unit for cooling, and then the coolant is conveyed to the cold section, and the first set value is larger than the second set value.
This embodiment is through setting up solitary unit of preheating, can accomplish waste heat discharge system's self-heating function, from this, the system need not other systems to participate in preheating before traditional waste heat discharge system puts into operation, and can leave the hot shutdown situation at the reactor and begin work to accomplish preheating work after satisfying waste heat discharge system access condition in a return circuit, thereby do not occupy the overhaul time, compressed the shutdown time of power plant, improved unit availability and core competitiveness.
In addition, the system has the advantages of safe operation method, simple operation, and excellent economical efficiency and operation capability.
In the present embodiment, the first and second electrodes are,
the waste heat discharge unit comprises a waste heat discharge pipe, a first valve bank, a cooling pump, a heat exchanger and a second valve bank, the waste heat discharge pipe is connected between a hot section of the reactor coolant system and a cold section of the reactor coolant system, the first valve bank, the cooling pump, the heat exchanger and the second valve bank are sequentially arranged on the waste heat discharge pipe, coolant in the hot section is pumped into the heat exchanger through the cooling pump to be cooled and then enters the cold section,
the preheating unit includes preheating pipe 25, heating structure 45, heat pump 46 and third valves, preheating pipe 25 is connected between the first intercommunication mouth and the second intercommunication mouth of waste heat discharge pipe, first intercommunication mouth is the position between second valves and the heat exchanger, the second intercommunication mouth is the position between first valves and the cooling pump, heating structure 45, heat pump 46 and third valves are located preheating pipe 25, coolant among the waste heat discharge unit is heated in the heat structure 45 of pump 46 pump income again to waste heat discharge unit.
In the present embodiment, the first and second electrodes are,
the third valve bank comprises a first preheating isolation valve 011 and a second preheating isolation valve 012, wherein the first preheating isolation valve 011 is arranged between a first communication port of the waste heat discharge pipe and the heating structure 45, and the second preheating isolation valve 012 is arranged between the heating pump 46 and a second communication port.
In the power plant operating situation, the third valve group is in a closed state, so that the preheating unit is isolated from the main pipeline (waste heat discharge pipe) of the waste heat discharge unit.
The heat pump 46 draws water from the main pipe downstream of the heat exchanger, and after being heated by the heating tank (heating structure 45), returns to the main pipe in front of the cooling pump, and circulates until the medium in the whole system loop outside the shell is uniformly heated to the temperature permitted by the residual coolant connected to the reactor.
Considering the heating capacity of the preheating unit and the water content of the residual heat discharge system, the preheating unit can heat the system to 120 ℃ within 3-4h, preheating operation is started when the reactor leaves a thermal shutdown condition, and the preheating operation is completed when a loop meets the residual heat discharge system access condition; after preheating is finished, the preheating unit is isolated from a main system pipeline, then an isolation valve between the preheating unit and a reactor coolant system is opened, and the waste heat discharge system starts to cool the reactor system until the reactor is brought to a cold shutdown state; in the starting process of the power plant, the preheating unit is isolated from a main system pipeline. Namely, the preheating unit is communicated with the main pipeline before being connected with the reactor coolant system only in the shutdown process of the power plant, and is isolated from the main pipeline of the system in other states.
During power plant power operation, the preheating unit is isolated from the main system pipeline (waste heat discharge pipe); the heating period is communicated. And after heating is finished, the residual heat removal system is isolated from the main pipeline of the system in the processes of cooling and heating of the reactor coolant system.
The preheating unit is used for heating the residual heat removal system to a temperature (the temperature difference between the temperature and the RCS is less than 60 ℃) which is suitable for being connected with a Reactor Coolant System (RCS), namely, the residual heat removal system is isolated from a main pipeline of the residual heat removal system.
And the preheated waste heat discharge unit pumps water to the hot pipe section of the Reactor Coolant System (RCS) loop 2, and returns to the cold pipe sections of the RCS loop 1 and the RCS loop 3 after being cooled by the waste heat discharge system. The residual heat removal unit has the capacity of bringing the reactor to and maintaining a cold shutdown state in the shutdown process during overhaul refueling, and the capacity of controlling the heating rate and bringing the reactor to 180 ℃ in the startup process.
The system is isolated from the reactor coolant system during power plant operation.
When the system is not available, the reactor can be brought to a cold shutdown state by other systems of the power plant, such as a safety injection system and a containment spraying system.
Wherein, the waste heat discharge pipe (main pipeline) is designed to bear the design parameters of a loop without cracking, and the design parameters of the preheating pipe 25 are lower than those of the main pipeline, so as to reduce the equipment investment and reasonably control the cost.
In the present embodiment, a small flow pipe 24 is further included, the small flow pipe 24 is connected between the first communicating port and the second communicating port of the waste heat discharging pipe, and the inner diameter of the small flow pipe 24 is smaller than the inner diameter of the waste heat discharging pipe. The small flow pipe 24 is used for preventing the pump from being damaged due to the fact that the cooling pump is blocked and the like under the conditions that a valve on a return section of the waste heat discharging pipe is suddenly closed, the pressure is suddenly increased and the like.
In the present embodiment, the first and second electrodes are,
the waste heat discharge pipe comprises a first bus section, a suction section, a second bus section, a cooling pump section, a third bus section, a heat exchanger section, a fourth bus section and a return section which are sequentially communicated along the flowing direction of the coolant,
the first parent section is in communication with the second loop hot section 21 of the reactor coolant system, the return section is in communication with the cold section of the reactor coolant system,
the cooling pump is arranged on the cooling pump section, the heat exchanger is arranged on the heat exchanger section,
the waste heat discharge pipe also comprises a bypass pipe section, and the bypass pipe section is connected between the third main section and the fourth main section.
In the present embodiment, the first and second electrodes are,
the heat exchanger section is equipped with two, and the heat exchanger is corresponding to be equipped with two, is first heat exchanger 43 and second heat exchanger 44 respectively, is equipped with the governing valve in the every heat exchanger section, also be equipped with the governing valve on the bypass pipe section, be the first governing valve 008 that corresponds with first heat exchanger 43 respectively, the second governing valve 009 that corresponds with second heat exchanger 44, the third governing valve 007 of locating on the bypass pipe section.
The bypass pipe section arranged on the heat exchange unit is used for controlling the cooling flow passing through the heat exchanger on the premise of maintaining the stable circulating flow of the whole system, so that the temperature reduction rate of the reactor coolant system in the shutdown process and the temperature rise rate of the reactor coolant system in the startup process are maintained within a target value range.
In this embodiment, the cooling pump section is equipped with two correspondingly, and the cooling pump is equipped with two correspondingly, is first cooling pump 40 respectively, and second cooling pump 41 all is equipped with the second check valve on the every cooling pump section, is the first check valve 005 that corresponds with first cooling pump 40 respectively, and the second check valve 006 that corresponds with second cooling pump 41.
In the present embodiment, the first and second electrodes are,
the first valve group comprises a first suction isolation valve and a second suction isolation valve,
the first suction isolation valves are positioned on the suction segments, the suction segments are positioned in the containment, the number of the suction segments is two, each suction segment is provided with two first suction isolation valves, the two first suction isolation valves on one suction segment are respectively an isolation valve 101 and an isolation valve 102, and the two first suction isolation valves on the other suction segment are respectively an isolation valve 201 and an isolation valve 202. A pressure locking device is arranged between the two first suction isolation valves of each suction segment, and when the pressure difference between the front isolation valve and the rear isolation valve is greater than 3.0MPa during the power plant power operation and the shutdown process, the isolation valves cannot be opened, so that the overpressure of the system caused by the false opening of the waste heat discharge system is prevented.
A second suction isolation valve 004 is located on the second parent section, which is located outside the containment.
In the present embodiment, the first and second electrodes are,
the second valve set includes a first return isolation valve, a first check valve, a return check valve 013, and a second return isolation valve 010.
The number of the return sections is two, one return section is connected with a first loop cold section 22 of the reactor coolant system, the other return section is connected with a third loop cold section 23 of the reactor coolant system, each return section is provided with a first return isolating valve, the isolating valve 103 corresponds to the first loop cold section 22, the isolating valve 203 corresponds to the third loop cold section 23, a first check valve, a check valve 104 corresponds to the first loop cold section 22 and a check valve 204 corresponds to the third loop cold section 23 are arranged between the corresponding cold section and the first return isolating valve on each return section.
The return check valve 013 and the second return isolation valve 010 are both located on a fourth female segment that passes through the containment, the return check valve 013 is located inside the containment, and the second return isolation valve 010 is located outside the containment.
In the present embodiment, the first and second electrodes are,
also included is a connecting tube connected between the bypass tube section and the chemical and volumetric control system.
When the pressure of a reactor coolant system cannot leak through a leak hole plate of the RCV system in the shutdown process of a power plant, the system is utilized to provide a pressure head for purification of the RCV system.
In the present embodiment, the first and second electrodes are,
the safety device further comprises a suction pipe, one end of the suction pipe is communicated with the part, located in the safety shell, of the second female section, and a safety valve 003 is arranged at the other end of the suction pipe.
The safety valve 003 is arranged on the suction port pipe connected with the main pipe of the suction port pipeline, so that after the system is connected into a reactor coolant system, when the reactor coolant system is suddenly boosted due to certain accidents, the safety valve 003 can perform overpressure protection on the system and the reactor coolant system; and in the normal power operation process of the power plant, when the isolation of an isolation valve between the system and a reactor coolant system fails, the safety valve 003 carries out overpressure protection on the system. The safety valve 003 discharges into the pressurizer pressure relief tank of the reactor coolant system or directly into the containment.
The application process of the waste heat removal system of the embodiment is as follows:
during plant power operation, the valves 101, 102, 201, 202, 103, 203 are closed, isolating the present system from the reactor coolant system, while the valves 010, 004, 007, 008, 009 are open. Valves 011 and 012 on the preheating pipe 25 are closed, and the preheating pipeline is isolated from the main pipeline, so as to prevent the failure of the preheating pipeline and equipment when the valves isolating the main pipeline of the system from the pipeline of the reactor coolant system fail.
When the power plant begins to cool down, the preheating of the system is synchronously started. And (3) opening valves 011 and 012, boosting the pressure in the loop to 2.5-3.0MPa by using the RCV system, and then opening a preheating tank and a preheating circulating pump to heat the medium in the main pipeline of the system.
When the temperature of the reactor coolant system of the power plant is reduced to 180 ℃, the system simultaneously completes the preheating of the system, and the requirement condition that the system is connected into the reactor coolant system is met. The valves 011 and 012 are closed, the preheating pipe 25 is isolated from the main pipeline of the system, then the valves 101, 102, 201, 202, 103 and 203 are opened, the cooling pumps 40 and 41 are started at the same time, and the reactor coolant system is cooled by the heat exchanger. Meanwhile, the regulation valves 007, 008 and 009 are used for maintaining the stability of the circulation flow of the system and maintaining the cooling rate of the reactor coolant system in a proper range, and the 007 is a closed-loop regulation valve which acts along with the action of the valves 008 and 009 to maintain the stability of the total flow.
And when all the fuel assemblies of the reactor core of the power plant are discharged to the spent fuel pool, the system is quitted from operation, and related maintenance operation of the system is carried out.
When the power plant is started, the valves 101, 102, 201, 202, 103 and 203 are opened, the valves 011 and 012 are closed, and the temperature rise rate of the reactor coolant system by using the system is controlled within a proper range until the temperature rises to 180 ℃ to reach the intervention condition of the system and the reactor coolant system. And (3) closing the valves 101, 102, 201, 202, 103 and 203, isolating the system from a reactor coolant system, continuously heating the reactor coolant system until the reactor coolant system reaches the power operation state of the power plant, naturally cooling the system to the normal temperature state, and recovering the standby state.
Example 2:
the embodiment provides a nuclear power system which comprises a reactor coolant system and a waste heat removal system in embodiment 1.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the utility model, and these modifications and improvements are also considered to be within the scope of the utility model.
Claims (10)
1. A residual heat removal system, comprising: a waste heat discharge unit and a preheating unit,
the preheating unit is connected between the inlet and the outlet of the residual heat discharging unit and used for forming circulation with the residual heat discharging unit when the residual heat discharging unit is disconnected with the reactor coolant system, and pumping the coolant in the residual heat discharging unit into the preheating unit for heating and then conveying the coolant back to the residual heat discharging unit,
the waste heat discharge unit is connected between a hot section and a cold section of the reactor coolant system and used for cooling the reactor coolant system to a first set value, and after the coolant in the waste heat discharge unit is heated to a second set value, the waste heat discharge unit is disconnected with the preheating unit and forms circulation with the reactor coolant system, and the coolant in the hot section is pumped into the waste heat discharge unit for cooling and then is conveyed to the cold section;
the first set value is greater than the second set value.
2. The residual heat removal system according to claim 1,
the waste heat discharge unit comprises a waste heat discharge pipe, a first valve bank, a cooling pump, a heat exchanger and a second valve bank, the waste heat discharge pipe is connected between a hot section of a reactor coolant system and a cold section of the reactor coolant system, the first valve bank, the cooling pump, the heat exchanger and the second valve bank are sequentially arranged on the waste heat discharge pipe, coolant in the hot section is pumped into the heat exchanger through the cooling pump to be cooled and then enters the cold section,
the preheating unit comprises a preheating pipe, a heating structure, a heating pump and a third valve group, the preheating pipe is connected between a first communicating port and a second communicating port of the waste heat discharging pipe, the first communicating port is the second valve group and the position between the heat exchangers, the second communicating port is the position between the first valve group and the cooling pump, the heating structure, the heating pump and the third valve group are arranged on the preheating pipe, and a coolant in the waste heat discharging unit is pumped into the heating structure through the heating pump to be heated and then returns to the waste heat discharging unit.
3. The residual heat removal system according to claim 2, further comprising a small flow pipe connected between the first communication port and the second communication port of the residual heat removal pipe, the small flow pipe having an inner diameter smaller than that of the residual heat removal pipe.
4. Waste heat removal system according to claim 2 or 3,
the waste heat discharge pipe comprises a first bus section, a suction section, a second bus section, a cooling pump section, a third bus section, a heat exchanger section, a fourth bus section and a return section which are sequentially communicated along the flowing direction of the coolant,
the first parent segment is communicated with the hot segment of the reactor coolant system, the return segment is communicated with the cold segment of the reactor coolant system,
the cooling pump is arranged on the cooling pump section, the heat exchanger is arranged on the heat exchanger section,
the waste heat discharge pipe also comprises a bypass pipe section, and the bypass pipe section is connected between the third female section and the fourth female section.
5. The residual heat removal system according to claim 4,
the first valve block includes a first intake isolation valve and a second intake isolation valve,
the first suction isolation valves are positioned on the suction sections, the suction sections are positioned in the containment, the number of the suction sections is two, each suction section is provided with two first suction isolation valves, a pressure locking device is arranged between the two first suction isolation valves of each suction section,
the second suction isolation valve is positioned on the second female section, and the second female section is positioned outside the containment.
6. The residual heat removal system according to claim 4,
the second valve bank includes a first return isolation valve, a first check valve, a return check valve, and a second return isolation valve,
the two return sections are provided, one return section is connected with the cold section of the first loop of the reactor coolant system, the other return section is connected with the cold section of the third loop of the reactor coolant system, each return section is provided with a first return isolating valve, a first check valve is arranged at the position, between the cold section and the first return isolating valve, of each return section,
the return check valve and the second return isolation valve are both located on the fourth female section, the fourth female section penetrates through the containment, the return check valve is located in the containment, and the second return isolation valve is located outside the containment.
7. The waste heat removal system of claim 4, wherein a plurality of heat exchangers are provided, a plurality of heat exchanger sections are correspondingly provided, each heat exchanger section is provided with a regulating valve, and the bypass pipe section is also provided with a regulating valve;
the cooling pump is equipped with a plurality ofly, and the cooling pump section is equipped with many correspondingly, all is equipped with the second check valve on the every cooling pump section.
8. The residual heat removal system according to claim 4, further comprising a connecting pipe connected between the bypass pipe section and the chemical and volumetric control system.
9. The residual heat removal system according to claim 4, further comprising a suction pipe, wherein one end of the suction pipe is communicated with the part of the second female section, which is located in the containment, and the other end of the suction pipe is provided with a safety valve.
10. A nuclear power system including a reactor coolant system and a residual heat removal system as claimed in any one of claims 1 to 9.
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| CN202121529424.9U CN215911200U (en) | 2021-07-06 | 2021-07-06 | Waste heat discharge system and nuclear power system |
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