Multi-module high-temperature gas cooled reactor nuclear power station water supply system and control method thereof

By setting up a water supply flow regulating valve and multiple variable frequency water supply pumps in the water supply system of a multi-module high-temperature gas-cooled reactor nuclear power plant, the pump group selector and controller can adjust the water supply flow and pressure between the reactor modules, and the reactor module is solved The lack of mutual backup between them improves the stability and reliability of the system and reduces the risk of shutdown.

CN119181519APending Publication Date: 2024-12-24CHINA POWER ENG CONSULTING GRP CORP EAST CHINA ELECTRIC POWER DESIGN INST
View PDF 0 Cites 0 Cited by

Patent Information

Application Number
CN202310742864.X
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2023-06-21
Publication Date
2024-12-24

AI Technical Summary

Technical Problem

The water supply system of multi-module high-temperature gas-cooled reactor nuclear power plant lacks the function of mutual backup between reactor modules, resulting in the pump group failure or pump jumping to manually switch the backup pump, which increases the risk of shutdown and affects the stability and economy of the system. reliability.

Method used

A multi-module high-temperature air-cooled reactor water supply system is designed. By setting up a water supply flow regulating valve and multiple variable frequency water supply pumps in each reactor module, the water supply flow and pressure of the steam generator inlet is realized by using the pump group selector and controller. Adjustment to ensure that the system output meets the water supply needs of the reactor module, and achieves modular control through isolation valves and pump hand-operated stations.

Benefits of technology

It improves the reliability of water supply of reactor modules, reduces the probability of shutdown accidents caused by switching of standby pumps, enhances the stability and flexibility of the system, realizes the resource sharing effect of water supply resources, and improves the flexible and reliable call capability of the equipment.

✦ Generated by Eureka AI based on patent content.

Smart Images

  • Figure CN119181519A_ABST
    Figure CN119181519A_ABST
Patent Text Reader

Abstract

The invention discloses a multi-module high-temperature gas cooled reactor nuclear power station water supply system and a control method thereof, and the system is characterized in that the system comprises a reactor module, a water supply module, a controller and a water supply flow regulating valve, and the control method comprises the following steps: determining the demand of the number of started pumps according to the commissioning condition of the reactor module; the demand information of the number of the starting pumps is sent to the pump set selection controller, and the pump set selection controller selects the pumps to be started according to the demand information of the number of the starting pumps, the current pump state information, the sequence selection information executed by the sequence selection operation panel and the like. And after the selected execution is finished, sending a specific pump starting instruction by combining the state information of the pump, the operation demand of the water supply system and other information. Compared with the prior art, the multiple variable-frequency water feeding pumps are achieved according to the pump set control function so as to meet the large value of the total requirement of the inlet mother pipe pressure of the steam generator of each reactor module and the inlet flow of the steam generator of each reactor module as the target, and it is ensured that the output of the water feeding system meets the water feeding requirement of the reactor module put into operation.
Need to check novelty before this filing date? Find Prior Art

Description

Technical Field

[0001] The invention relates to a water supply system for a nuclear power plant, and in particular to a water supply system for a multi-module high-temperature gas-cooled reactor nuclear power plant and a control method thereof. Background Art

[0002] The modular high temperature gas-cooled reactor nuclear power plant is one of the main promotion technologies of the fourth generation of nuclear power. It is based on the pebble bed modular high temperature gas-cooled reactor technology and has the characteristics of inherent safety, low nuclear waste emissions and effective prevention of nuclear proliferation. The modular configuration of the multi-module high temperature gas-cooled reactor makes it flexible. At the same time, it is different from the traditional pressurized water reactor or boiling water reactor nuclear power plant, which is a one-to-one solution. The control technology of one-to-one is mature.

[0003] The modular construction and operation characteristics of multi-module reactor nuclear power plants make it one of the main technical issues how to match the water supply system settings with the characteristics of the reactor module settings and have flexible and reliable control functions.

[0004] In the prior art, each reactor module is provided with a single high-pressure heater, which cannot achieve the function of mutual backup. In addition, each reactor module is provided with an independently used electric speed-regulating feedwater pump and its pre-pump, so that the reactor module is too much restrained by the pump group. When a pump group failure or other pump tripping occurs, the operator manually switches the backup pump. The switching process must meet the helium-water flow ratio of the first and second circuits required by the nuclear island, so that the system can continue to operate. If the backup pump fails to be put into operation, the reactor corresponding to the steam generator supplied by it will be shut down urgently. The stability of the reactor operation of this scheme is directly related to the influence of pump switching, which increases the risk of shutdown, and the implicit economic reliability needs to be improved. The water supply system of a high-temperature gas-cooled reactor nuclear power plant with multiple modules (more than two) must not only meet the stability and reliability of the system but also take into account the flexibility of the construction and commissioning of its reactor modules. Therefore, a water supply system and a control method for a multi-module high-temperature gas-cooled reactor nuclear power plant are needed. Summary of the invention

[0005] The purpose of the present invention is to invent a multi-module high temperature gas-cooled reactor feedwater system and a control method thereof, wherein the feedwater flow rate at the steam generator inlet of each reactor module is adjusted by a feedwater flow regulating valve arranged at the steam generator inlet. The multiple variable frequency feedwater pumps are implemented according to the pump group control function to meet the larger value of the main pipe pressure at the steam generator inlet of each reactor module and the total flow rate at the steam generator inlet of each reactor module, so as to ensure that the output of the feedwater system meets the feedwater demand of the reactor module in operation. It discloses that the present application discloses a water supply system for a multi-module high-temperature gas-cooled reactor nuclear power plant, the system comprising: a reactor module, a water supply module, a controller, a water supply flow regulating valve, and a pump manual operation station, wherein: the reactor module comprises a plurality of nuclear island modules, the plurality of nuclear island modules are provided with water supply inlets and are respectively connected to the water supply modules, and isolation valves are provided one by one between the plurality of nuclear island modules and the water supply modules according to the number of the nuclear island modules; the water supply flow regulating valve is provided one by one according to the number of nuclear island modules like the isolation valve; the water supply module is provided with a water supply pump, the water supply pump is connected to the pump manual operation station and the controller; the controller comprises a first controller and a second controller, the pump manual operation station comprises a pump group manual operator and pump manual operators corresponding to the number of the plurality of nuclear island modules.

[0006] In a preferred example, the first controller is used to control the water supply mother pipe pressure of the steam generator inlet of each nuclear island module at a set value, and the second controller is used to control the water supply flow rate at the steam generator inlet of each nuclear island module to meet the water supply flow rate demand corresponding to the power of each nuclear island module.

[0007] In a preferred example, the water supply system is further configured with a pump group selector, and the pump group selector is configured to implement the calling and exiting functions of the water supply pump.

[0008] In a preferred example, the pump group selector is configured with an operation panel, which can display the code, name, and status information of the pump group selection controller, and can also set the pump number requirement and pump sequence information; the operation panel also displays the run / stop information, automatic / manual, available / unavailable and running time information of each pump, and the operation panel is configured with a rotation automatic / manual button, a rotation start / stop button, a rotation time setting input window, a suspend button, and a pump sequence setting button

[0009] In a preferred example, the water supply system further includes a rate change limiter, which is configured to limit excessive changes in control instructions of the first controller and the second controller from causing system fluctuations.

[0010] In a preferred example, the water supply module also includes: a high-pressure cylinder, a low-pressure cylinder, a condenser, a condensate pump, a low-pressure heater, a high-pressure heater and a deaerator.

[0011] In a preferred example, a tracking module is configured in the pump manual operation station.

[0012] The present invention also discloses a control method, which comprises the following steps:

[0013] (1) Determine the commissioning status of the nuclear island module

[0014] First of all, the specific number of nuclear island modules to be put into operation in the reactor module needs to be determined based on the actual situation.

[0015] (2) Start the feedwater pump according to the number of nuclear island modules put into operation

[0016] By using the pump group selection controller and based on the required number of pumps to be started, the current pump status information, the sequence information executed by the sequence selection operation panel, etc., the pump to be started is selected. After the selection is completed, the command to start a specific pump is sent in combination with the pump status information and the water supply system operation requirements.

[0017] (3) Adjust the water flow rate to meet the water supply needs of the corresponding nuclear island module

[0018] By setting a first controller for controlling the water supply main pipe pressure of the steam generator inlet of each nuclear island module at a set value and a second controller for controlling the water supply flow rate of the steam generator inlet of each nuclear island module to meet the water supply flow rate demand corresponding to the power of each nuclear island module. And a rate change limiter that collects the maximum value of the output of the first controller and the second controller is used to limit the fluctuation of the system caused by excessive changes in the control instructions. After the setting is completed, multiple variable frequency feed water pumps are implemented through the first controller and the second controller according to the control function of the pump group to meet the larger value of the steam generator inlet main pipe pressure of each reactor module and the total demand of the steam generator inlet flow of each reactor module, so as to ensure that the output of the feed water system meets the water supply demand of the commissioned reactor module.

[0019] In a preferred embodiment, the step (2) further comprises the following sub-steps:

[0020] The water supply pumps in the water supply system are sequenced. The sequence selection operation starts according to the current initial state of the operation panel. Click on the point control units in the control panel matrix at will according to the order to be set. For example, you can first select the pump role of sequence 2 as pump C, or you can first select pump B in sequence 1. When a point control unit is selected, the column unit and row unit of the corresponding matrix are automatically invalidated. Next, you can still select the required units from the remaining valid point control units in the required order. The point control unit selected for the second time will again automatically invalidate the remaining valid units in the corresponding column and the corresponding row. After the point control unit is selected for the third time according to the above rules, the automatic invalidation function is executed again. At this point, there will be only one valid point control unit in the matrix of the sequence selection operation panel, and it will be automatically set to the selected state.

[0021] In a preferred example, the control method also includes a manual operation mode, which is implemented by the pump manual operation station through its components and a matching tracking module. The functions of the tracking module include a single pump manual operation station tracking function and a pump group manual operation station tracking function. The single pump manual operation station tracking function is to activate the tracking module of the corresponding pump manual operation station when the corresponding pump is not in operation or the corresponding pump manual operation station is in manual mode, and the tracking module tracks the control instruction signal of the corresponding pump to the corresponding pump manual operation station. The pump group manual operation station tracking function is to activate the tracking module of the pump group manual operation station when the pump manual operation station is in automatic mode and the corresponding pump has not been running or the pump group manual operation station is in manual mode, and the tracking module tracks the maximum value signal in the control instruction of each manual operation station outlet to the pump group manual operation station.

[0022] The main advantages of the present invention are:

[0023] (1) The invention proposes a water supply system for a multi-module high-temperature gas-cooled reactor nuclear power plant. The idea of ​​its setting is to regard the multi-module high-temperature gas-cooled reactors of the nuclear power plant as water demanders, which share a water resource pool with reliable capacity. The water resource pool is equipped with a water pump that can meet the maximum user demand for water supply pressure delivery. The purpose of water supply delivery is not a single pump corresponding to a single reactor demander, but to integrate the water supply main pipe pressure demand and the power matching water demand of the reactor module demander at a certain moment, so as to achieve the effect of resource sharing of water resources. The flexible and reliable calling between the redundant water supply system equipment improves the reliability of the reactor module water supply, and greatly reduces the probability of shutdown accidents caused by the switching of standby pumps in the aforementioned prior art.

[0024] (2) The water supply system for a multi-module high-temperature gas-cooled reactor nuclear power plant proposed in the present invention has independent water supply operating devices at the water supply interface of each reactor module, including isolation valves, regulating valves, detection elements, etc., so that the reactor module has a modular water supply interface, which can be independently connected and exited as a water demander according to the operation status of the reactor. At the same time, the water supply flow regulating valve arranged at the entrance of each reactor module plays the function of finely adjusting the water supply flow, so that it meets the specific requirements of the actual operation of the corresponding reactor module. At the same time, the setting of the water supply pump group in the water supply system proposed in the present invention can also be constructed in batches according to the construction status of the reactor module. The control method of the water supply system proposed in the present invention makes the control of different water supply pumps based on the modular implementation method, and each independent module will not affect the main controller implementation scheme of the water supply pump frequency regulation control method, and each pump has a corresponding independent operation function implementation, and its expansion only needs to add the corresponding independent function in a modular manner, and the implementation method is flexible and reliable.

[0025] (3) The implementation method of the pump group selection controller proposed in the present invention determines the demand for the number of starting pumps according to the commissioning status of the reactor module. The demand information for the number of starting pumps is sent to the pump group selection controller. The pump group selection controller selects the pump to be started based on the demand information for the number of starting pumps, the current pump status information, the sequence information executed by the sequence operation panel, etc. After the selection is completed, the command to start a specific pump is sent in combination with the pump status information and the water supply system operation requirements. The pump operation rotation function, the running pump fault switching function, and the function of calling and exiting according to the real-time pump demand taking into account the sorting information are comprehensively considered, so that the water supply system pool setting and the overall coordinated calling of the conveying equipment can be realized, the stability of the system is enhanced, and the equipment operation and maintenance requirements are taken into account.

[0026] (4) The method for realizing the pump sequence selection function by sequential elimination and the sequence selection operation panel based on the matrix array mode of the point control unit proposed in the present invention make the realization of the pump sequence setting function convenient, fast and flexible, and have very good scalability. When adding equipment, its panel elements and internal control methods only need to be expanded in a modular manner without overturning and redoing. At the same time, this method ensures the realization of any sorting function from the selection mechanism, and is not limited to only a few fixed sorting buttons, realizing the full sorting function in the true sense.

[0027] A large number of technical features are recorded in the specification of this application, which are distributed in various technical solutions. If all possible combinations of technical features of this application (i.e., technical solutions) are to be listed, the specification will be too long. In order to avoid this problem, the various technical features disclosed in the above-mentioned invention content of this application, the various technical features disclosed in the various embodiments and examples below, and the various technical features disclosed in the accompanying drawings can be freely combined with each other to form various new technical solutions (these technical solutions are all deemed to have been recorded in this specification), unless the combination of such technical features is technically infeasible. For example, in one example, feature A+B+C is disclosed, and in another example, feature A+B+D+E is disclosed, and features C and D are equivalent technical means that play the same role. Technically, only one can be used, and it is impossible to use them at the same time. Feature E can be combined with feature C technically. Then, the solution of A+B+C+D should not be deemed to have been recorded because it is technically infeasible, and the solution of A+B+C+E should be deemed to have been recorded. BRIEF DESCRIPTION OF THE DRAWINGS

[0028] Figure 1 is a schematic diagram of a water supply system for a multi-module high temperature gas-cooled reactor nuclear power plant according to an embodiment of the present invention;

[0029] Figure 2 is a control scheme diagram of a water supply system for a multi-module high temperature gas-cooled reactor according to an embodiment of the present invention;

[0030] Figure 3 It is a flowchart of a method for implementing the tracking function of a tracking module according to an embodiment of the present invention.

[0031] Figure 4 is a flowchart of a method for realizing the function of a pump group selection controller according to an embodiment of the present invention;

[0032] Figure 5 Schematic diagram of a method for realizing a function preamble signal of a pump group selection controller according to an embodiment of the present invention;

[0033] Figure 6 is a schematic diagram of a method for realizing the function of a pump group selection controller according to an embodiment of the present invention;

[0034] Figure 7 is a schematic diagram of an operation panel of a pump group selection controller according to an embodiment of the present invention;

[0035] Figure 8 is a schematic diagram of a sequence selection operation panel according to an embodiment of the present invention;

[0036] Fig. 9 is a schematic diagram of a signal function setting of a point control unit according to an embodiment of the present invention;

[0037] Fig.10 is a flowchart of a sequence selection operation panel control method according to an embodiment of the present invention;

[0038] Fig.11 is a control effect and flow chart of a sequence selection operation panel according to an embodiment of the present invention; DETAILED DESCRIPTION

[0039] After careful and in-depth research, the inventors have developed for the first time a multi-module high-temperature gas-cooled reactor water supply system and a control method thereof. Compared with the prior art, the present invention can achieve the effect of resource sharing of water supply resources. The flexible and reliable calling of redundantly set water supply system equipment improves the reliability of water supply to the reactor module, greatly reducing the probability of shutdown accidents caused by standby pump switching in the aforementioned prior art. In addition, the control method of the water supply system corresponding to the present invention makes the control of different water supply pumps based on a modular implementation method, and each independent module will not affect the main controller implementation scheme of the water supply pump frequency regulation control method, and makes Each pump has a corresponding independent operating function, and its expansion only requires the corresponding independent function to be added in a modular manner. The implementation method is flexible and reliable. Moreover, the implementation method of the pump group selection controller proposed in the present invention can determine the demand for the number of starting pumps according to the commissioning status of the reactor module. The demand information for the number of starting pumps is sent to the pump group selection controller. The pump group selection controller selects the pump to be started based on the demand information for the number of starting pumps, the current pump status information, the sequencing information executed by the sequencing operation panel, etc. After the selection is completed, the command to start a specific pump is sent in combination with the pump status information and the water supply system operation requirements. The pump operation sequence function, the running pump fault switching function, and the function of calling and exiting according to the real-time pump demand taking into account the sorting information are comprehensively considered, so that the water supply system pool setting and the overall coordinated calling of the conveying equipment can be realized, the stability of the system is enhanced, and the needs of equipment operation and maintenance are taken into account. In addition, the method of realizing the pump sequence selection function using sequential elimination and the sequence selection operation panel based on the matrix array mode of the point control unit proposed in the present invention make the realization of the pump sequence setting function convenient, fast and flexible, and the scalability is very good. When adding equipment, its panel elements and internal control methods only need to be expanded modularly without overturning and redoing. At the same time, this method ensures the realization of any sorting function from the selection mechanism, and is not limited to only a few fixed sorting buttons, realizing the full sorting function in the true sense.

[0040] Example

[0041] In order to make the objectives, technical solutions and advantages of the present application clearer, the implementation methods of the present application will be further described in detail below in conjunction with the accompanying drawings.

[0042] The first embodiment of the present invention relates to a modular high temperature gas-cooled reactor water supply system and a control method thereof, wherein the water supply system is as follows: Figure 1 As shown, it includes: a reactor module, a water feed module, a controller, a water feed flow regulating valve, and a pump manual operation station, wherein: the reactor module includes a plurality of nuclear island modules, the plurality of nuclear island modules are provided with water feed inlets, and are respectively connected to the water feed modules, and isolation valves are provided one by one between the plurality of nuclear island modules and the water feed modules according to the number of the nuclear island modules; the water feed flow regulating valve is provided one by one according to the number of nuclear island modules like the isolation valve; the water feed module is provided with a water feed pump, and the water feed pump is connected to the pump manual operation station and the controller; the controller includes a first controller and a second controller, and the pump manual operation station includes a pump group manual operator and pump manual operators corresponding to the number of the plurality of nuclear island modules. In this embodiment, the first controller is used to control the water supply mother pipe pressure of the steam generator inlet of each nuclear island module at a set value, and the second controller is used to control the water supply flow rate of the steam generator inlet of each nuclear island module to meet the water supply flow rate demand corresponding to the power of each nuclear island module. The water supply system is also equipped with a pump group selector, which is configured to realize the call and exit functions of the water supply pump, and the pump group selector is equipped with an operation panel, which can set the code, name, and status information of the pump group selection controller, and can also set the pump number demand and pump sequence information; the operation panel also displays the operation / stop information, automatic / manual, available / unavailable and operation time information of each pump, and the operation panel is equipped with a rotation automatic / manual button, a rotation start / stop button, a rotation time setting input window, a hang-up button, and a pump sequence setting button. In this embodiment, the water supply module also includes: a high-pressure cylinder, a low-pressure cylinder, a condenser, a condensate pump, a low-pressure heater, a high-pressure heater and a deaerator, and a tracking module in the pump operator station.

[0043] In this embodiment, taking module 1 as an example, manual stop valves VV11 and VV15 are set in its corresponding water supply passage to meet the function of separate isolation and maintenance. Check valves VV12 and VV13 are set to avoid water backflow. Electric isolation valves MOV11 and MOV13 are set to realize the automatic start or exit of the module water supply function. Flow detection element F11 and pneumatic feed water flow control valve FCV11 are set to complete the monitoring and regulation of the feed water flow at the steam generator inlet of module 1. At the same time, pressure detection elements are set near the feed water inlet main pipe of the multi-module reactor near each module feed water intake point to monitor the pressure value of the reactor feed water inlet main pipe.

[0044] The control method of the water supply system of a multi-module high temperature gas-cooled reactor nuclear power plant used in this embodiment is characterized in that the method comprises the following steps:

[0045] (1) Determine the commissioning status of the nuclear island module

[0046] First of all, the specific number of nuclear island modules to be put into operation in the reactor module needs to be determined based on the actual situation.

[0047] (2) Start the feedwater pump according to the number of nuclear island modules put into operation

[0048] By using the pump group selection controller and based on the required number of pumps to be started, the current pump status information, the sequence information executed by the sequence selection operation panel, etc., the pump to be started is selected. After the selection is completed, the command to start a specific pump is sent in combination with the pump status information and the water supply system operation requirements.

[0049] (3) Adjust the water flow rate to meet the water supply needs of the corresponding nuclear island module

[0050] By setting a first controller for controlling the water supply main pipe pressure of the steam generator inlet of each nuclear island module at a set value and a second controller for controlling the water supply flow rate of the steam generator inlet of each nuclear island module to meet the water supply flow rate demand corresponding to the power of each nuclear island module. And a rate change limiter that collects the maximum value of the output of the first controller and the second controller is used to limit the fluctuation of the system caused by excessive changes in the control instructions. After the setting is completed, multiple variable frequency feed water pumps are implemented through the first controller and the second controller according to the control function of the pump group to meet the larger value of the steam generator inlet main pipe pressure of each reactor module and the total demand of the steam generator inlet flow of each reactor module, so as to ensure that the output of the feed water system meets the water supply demand of the commissioned reactor module.

[0051] The control method of this embodiment is that the feedwater flow rate at the steam generator inlet of each reactor module is adjusted by the feedwater flow rate regulating valve set at the steam generator inlet. The multiple variable frequency feedwater pumps are implemented according to the pump group control function to meet the larger value of the main pipe pressure at the steam generator inlet of each reactor module and the total flow rate demand at the steam generator inlet of each reactor module, so as to ensure that the output of the feedwater system meets the feedwater demand of the commissioned reactor module. For details, see Figure 2. Among them, the reactor module is connected to the water supply system as the demand side, that is, when a reactor module is not put into operation, its corresponding water supply electric isolation valve is closed, and it does not participate in the water supply system supply. When a reactor module is put into operation, the corresponding water supply electric isolation valve is opened. Taking module 1 as an example, MOV11 and MOV13 are automatically opened, and the reactor module 1 starts to use water supply. At this time, the feed water flow control valve FCV11 at the inlet of the steam generator of reactor module 1 adjusts the feed water flow according to the power demand of reactor module 1 to meet the water supply demand of the nuclear island. The feed water pump frequency control function adopts the method of dual-loop controller and independent manual operation station to realize the feed water pump frequency simulation control function, and adopts the method of pump group selection controller to realize the call and exit of specific pumps. The specific method of the feed water pump frequency simulation control function is to set controller 1 to control the pressure of the steam generator inlet feed water main pipe of each nuclear island module at the set value, and set controller 2 to control the feed water flow supply at the steam generator inlet of each nuclear island module to meet the feed water flow demand corresponding to the power of each nuclear island module. The output of controller 1 and controller 2 takes the larger value and sends it to the rate change limiter to limit the fluctuation of the system caused by excessive changes in the control command. At the same time, in order to increase the flexibility of system operation, the pump group hand operator, pump A hand operator, pump B hand operator, pump C hand operator, and pump D hand operator are set to provide flexible and diverse operation modes for the pump group and the single pump. Considering that the distance span of the mother pipe is large and there is pressure loss between different points, pressure detection points are set near the water inlet of the 6 modules, and the average pressure value corresponding to the reactor module in use is selected when the water supply pump frequency control loop is used.

[0052] In this embodiment, since the setting of the hand operator integrates the setting of the pump group and the single pump hand operator, the realization of the tracking function has an important impact on the smooth operation of the entire system. Based on this, this paper proposes a method for realizing the tracking function of the water supply pump group as follows.

[0053] The single pump manual operation station tracking function activates the tracking module of the corresponding pump manual operation station when the corresponding pump is not in operation or the corresponding pump manual operation station is in manual mode. The tracking module tracks the control command signal of the corresponding pump to the corresponding pump manual operation station.

[0054] The pump group manual operation station tracking function activates the tracking module of the pump group manual operation station when the pump A / B / C / D manual operation station is in automatic mode and the corresponding pump is not running or the pump group manual operation station is in manual mode. The tracking module tracks the maximum value signal in the export control command of each pump A / B / C / D manual operation station to the pump group manual operation station.

[0055] The controller setting value tracking function is to trigger the corresponding switching module to start the controller setting value tracking feedback value when the pump A / B / C / D manual operation stations are all in manual mode or any pump manual operation station is in manual mode and the corresponding pump is running. Specifically, the controller 1 setting value tracks the steam generator inlet feedwater main pipe pressure detection value, and the controller 2 setting value tracks the sum of the steam generator inlet feedwater flow detection value. For details of the flow chart of the tracking function implementation method, see Figure 3 .

[0056] In this embodiment, the implementation method of the pump group selection controller determines the demand for the number of starting pumps according to the commissioning status of the reactor module, and the demand information for the number of starting pumps is sent to the pump group selection controller. The pump group selection controller selects the pump to be started based on the demand information for the number of starting pumps, the current pump status information, the sequencing information executed by the sequencing operation panel, etc. After the selection is completed, the command to start a specific pump is sent in combination with the pump status information and the water supply system operation requirements.

[0057] The required number of startup pumps is determined based on the operation status of the reactor module and the pump selection information. Figure 1 A 6-module high-temperature gas-cooled reactor is proposed, with 4X33% feedwater pumps. When all modules are put into operation and the full load is running, the number of feedwater pumps in use can be set as follows:

[0058] Operation module <= 2, start one water supply pump and keep three as standby;

[0059] Operation module <= 4, start 2 water supply pumps and keep 2 as standby;

[0060] Operation module>4, start 3 water supply pumps and keep 1 as standby.

[0061] Of course, the water supply system can also be constructed in batches according to the construction of the reactor modules. For example, when two reactor modules are constructed in a short period of time, only two water supply pumps can be installed, one for use and one for backup. When four reactor modules are constructed in a short period of time, only three water supply pumps can be installed, two for use and one for backup. When other reactor modules are subsequently constructed, the water supply system will increase its capacity accordingly, which is very flexible. When the number of configured water supply pumps matches the construction of the reactor modules but does not reach the maximum number of 4, the above-mentioned backup number can be reduced accordingly, and the realization of its control function will not be affected.

[0062] When a reactor module is exited, the corresponding main steam electric isolation valve and feedwater electric isolation valve are closed, and the feedwater supply to the module ends.

[0063] The method to realize the pump group selection controller function is as follows:

[0064] First, check whether the pump group selection controller is not suspended. If not, all point control units are set to unavailable state, that is, each point control unit in the selection operation panel cannot perform point selection operation. If yes, enter the pump group selection controller operation panel.

[0065] Press the "Pump Sequence Setting" button to enter the sequence selection operation panel to execute the pump sequence setting function. After the pump sequence setting function is completed, the modular function will be entered. For the convenience of description, pump A is used as an example. The implementation method of other pump modules is the same.

[0066] If the pump group selection controller is not suspended, then enter the judgment unit to see if pump A is in manual state? If so, continue to judge whether pump A is in running state? If so, pump A is selected. Otherwise, pump A is not selected. If pump A is not in manual state, then continue to enter the judgment unit to see if pump A is selected on the sequence selection operation panel. At the same time, after the pump sequence setting function is executed, it is synchronously sent to the judgment unit to judge whether pump A is selected on the sequence selection operation panel? If not, pump A is not selected. If yes, then enter to judge whether the number of pumps to be started and run has not been met? If yes, pump A is not selected. If yes, then judge whether pump A is ranked first among the non-running pumps? If yes, pump A is selected. Otherwise, pump A is not selected. In addition, if pump A is selected on the sequence selection operation panel, it will be sent in parallel to the judgment unit to see if the rotation operation mode has been started? If not, continue to judge whether the selected sequence number of pump A is less than the required number of pumps? If yes, pump A is selected. Otherwise, pump A is not selected. If the rotation operation mode has been started, the judgment is continued to be executed, whether the rotation mode operation timer of pump A has expired? If so, pump A is not selected. If not, pump A is selected. When the rotation mode has been started, it is sent to the subsequent judgment unit in parallel to determine whether the rotation mode operation timer of pumps B / C / D has expired? If not, pump A is selected. If so, it is continued to determine whether pump A is ranked first among the non-operating pumps? If so, pump A is selected. Otherwise, pump A is not selected. The node where pump A is selected continues to be sent to the judgment module to determine whether pump A is not in an unavailable state? If not, pump A is not selected. If so, the judgment is continued to be executed, whether pump A is in the operating state? If not, the start pump A command is executed. If so, the stop pump A command is executed. As mentioned above, if pump A is in the operating state, it will also be sent to the judgment unit synchronously to determine whether the number of pumps started and running exceeds the limit? If not, the start pump A command is maintained. If yes, the stop pump A command is executed. As mentioned above, if pump A is in the operating state, it will also be sent to the judgment unit synchronously to determine whether the number of pumps started and running exceeds the limit? If not, the start pump A command is maintained. If yes, then determine whether pump A is the last one in the running pumps. If no, keep starting pump A. If yes, execute the stop pump A. If pump A is not selected, the node continues to send the judgment unit whether pump A is in running state. If yes, execute the stop pump A. If no, keep starting pump A. See Figures 4 to 6 .

[0067] The effect of the method for pump group selection control of the water supply system of a multi-module high-temperature gas-cooled reactor nuclear power plant proposed in the present invention is closely related to the pump group selection implementation, so the present invention proposes a corresponding pump selection sequence implementation method.

[0068] The pump group selection controller operation panel used with the present invention is as follows Figure 7 As shown, the code, name, and status information of the pump group selection controller are set, and the pump number requirement and pump sequence information are set. The operation panel also displays the run / stop information, automatic / manual, available / unavailable, and operation time information of each pump. At the same time, the rotation automatic / manual button, rotation start / stop button, and rotation time setting input window are set. The suspend button and pump sequence setting button are set at the bottom of the operation panel. Pressing the pump sequence setting button will call up the sequence selection operation panel, such as Figure 8 shown.

[0069] The overall sequence selection operation panel is designed in a matrix array mode. The lock / unlock button is set in the upper left corner of the panel, and the serial number indicator label is set in the first row of the panel to indicate the information of "Sequence 1", "Sequence 2", "Sequence 3" and "Sequence 4". The pump label is set in the first column of the panel to indicate the information of "Pump A", "Pump B", "Pump C" and "Pump D". The 4X4 inner matrix area contained in the operation panel is the point control unit area, which is used for specific selection control and display of sequence selection information.

[0070] The lock / unlock button provides lock and unlock functions. When the button is pressed, it is in the locked state, and the information on the button surface indicates "locked". When it is released, the unlock function is executed, and the information on the button surface indicates "unlocked".

[0071] When the "lock" function is triggered, the current state of the sequence operation panel is locked, and each point control unit in the control matrix is ​​in an inoperable state. When the "unlock" function is triggered, the current state of the sequence operation panel is unlocked, and each point control unit in the control matrix is ​​in an operable state (when the pump is in an available state) or an inoperable state (when the pump is in an unavailable state).

[0072] The point control unit is a button indicator unit located at each matrix element position in the 4X4 control matrix. It is an integrated unit device with a button operation function. When the button is pressed, its indication turns green, indicating that the point control unit is selected and the sequence selection function it executes has been implemented. When the button is not pressed, it has two status displays. One is blue, indicating that its current status is that the corresponding pump is available, and the point control unit is in an operable state and has not been selected. The other is gray, indicating that its current status is inoperable. The corresponding reason may be that the pump status is unavailable or it is inoperable due to the sequence selection logic.

[0073] For the point control unit corresponding to pump A sequence 1, for the convenience of description, it is named point control unit A1, and the device is pump A, and the sequence number is 1. Among them, the signal SC-A1-1, that is, the point control unit A1 is selected, is set to 1 when the point control unit is selected, otherwise, its value is 0. The signal SC-A1-2, that is, the point control unit A1 is unavailable / available, is set to 1 when the pump A device is unavailable, otherwise, its value is 0. The priority of signal SC-A1-2 is higher than that of signal SC-A1-1, that is, no matter whether the unit is selected or not, as long as the receiving device body signal confirms that it is unavailable, the point control unit A1 unavailable signal is set to 1. For details, see Fig. 9

[0074] The sequence selection operation starts according to the current initial state of the operation panel. The initial state of the operation panel is automatically matched according to the current state of the connected pump. The method is as follows. When the sequence selection is not executed, the number of available pumps = the number of available pumps in the sequence selection. If only pump A, pump B and pump D are available at present, all the point control units in the sequence 4 column are automatically grayed out, and all the point control units in the corresponding row of pump C and the corresponding column of sequence 4 are automatically grayed out. This method makes the valid operation units always displayed on the sequence selection operation panel, so that the selection operation is selected in the smallest and optimal area range.

[0075] The control method of the sequence selection operation panel is implemented according to the idea of ​​sequential elimination, as follows:

[0076] The sequence selection operation starts according to the current initial state of the operation panel. Click on any point control unit in the control panel matrix in the order you need to set. For example, you can first select the pump role of sequence 2 as pump C, or you can first select pump B in sequence 1. When a point control unit is selected, the corresponding column unit and row unit of the matrix are automatically set to invalid. Next, you can still select the required unit from the remaining valid point control unit range in the required order. The point control unit selected for the second time will again automatically invalidate the remaining valid units in the corresponding column and the corresponding row. After the point control unit is selected for the third time according to the above rules, the automatic invalidation function is executed again. At this point, there will be only one valid point control unit in the matrix of the sequence selection operation panel, which will be automatically set to the selected state. See the control method scheme diagram of the sequence selection operation panel for details. Take the final setting of the pump sequence as pump A-pump D-pump C-pump B as an example to illustrate one of the operation implementation methods, such as Fig.11As shown in the control effect of the sequence selection operation panel and Figure B in the flow chart, in this sequence selection operation step 1, pump A is selected as the sequence 1 pump, then the sequence 2-4 units in the row where pump A is located are automatically set to invalid, and pumps B / C / D in the column where sequence 1 is located are automatically set to invalid. In this sequence selection operation step 2, pump B is selected as the sequence 4 pump, then the sequence 2 / 3 units in the row where pump B is located are automatically set to invalid, and pumps C / D in the column where sequence 4 is located are automatically set to invalid. In step 3, pump D is selected as the sequence 2 pump, then the sequence 3 unit in the row where pump D is located is automatically set to invalid, and pump C in the column where sequence 2 is automatically set to invalid. At this time, only pump C sequence 3 remains in an operable state, and the remaining units are in an inoperable state or a selected state, so they are automatically set to a selected state and are located in sequence 3. See details. Figure 10-11 .

[0077] It should be noted that in the invention document of this patent, relational terms such as first and second are only used to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Moreover, the terms "include", "comprise" or any other variants thereof are intended to cover non-exclusive inclusion, so that the process, method, article or device including a series of elements includes not only those elements, but also other elements not explicitly listed, or also includes elements inherent to such process, method, article or device. In the absence of further restrictions, the elements defined by the sentence "including one" do not exclude the existence of other identical elements in the process, method, article or device including the element. In the invention document of this patent, if it is mentioned that an action is performed according to an element, it means that the action is performed at least according to the element, which includes two situations: performing the action only according to the element, and performing the action according to the element and other elements. Expressions such as multiple, multiple, and multiple include 2, 2 times, 2 kinds, and more than 2, more than 2 times, and more than 2 kinds.

[0078] All documents mentioned in the present invention are considered to be included in the disclosure of the present invention as a whole, so that they can be used as the basis for modification when necessary. In addition, it should be understood that the above are only preferred embodiments of this specification and are not used to limit the scope of protection of this specification. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of one or more embodiments of this specification should be included in the scope of protection of one or more embodiments of this specification.

Claims

1. A water supply system for a multi-module high temperature gas-cooled reactor nuclear power plant, characterized in that: The system includes: a reactor module, a water feed module, a controller, a water feed flow regulating valve, and a pump manual operation station, wherein: the reactor module includes a plurality of nuclear island modules, the plurality of nuclear island modules are provided with water feed inlets and are respectively connected to the water feed modules, and isolation valves are provided one by one between the plurality of nuclear island modules and the water feed modules according to the number of the nuclear island modules; the water feed flow regulating valve is provided one by one according to the number of nuclear island modules like the isolation valve; the water feed module is provided with a water feed pump, and the water feed pump is connected to the pump manual operation station and the controller; the controller includes a first controller and a second controller, and the pump manual operation station includes a pump group manual operator and pump manual operators corresponding to the number of the plurality of nuclear island modules.

2. The water supply system according to claim 1, characterized in that: The first controller is used to control the water supply main pipe pressure of the steam generator inlet of each nuclear island module at a set value, and the second controller is used to control the water supply flow rate at the steam generator inlet of each nuclear island module to meet the water supply flow rate demand corresponding to the power of each nuclear island module.

3. The water supply system according to claim 1, characterized in that: The water supply system is also equipped with a pump group selector, and the pump group selector is configured to realize the calling and exiting functions of the water supply pump.

4. The water supply system according to claim 3, characterized in that: The pump group selector is equipped with an operation panel, which can set the code, name, status information of the pump group selection controller, and can also set the pump number requirement and pump sequence information; the operation panel also displays the run / stop information, automatic / manual, available / unavailable and running time information of each pump, and the operation panel is equipped with a rotation automatic / manual button, a rotation start / stop button, a rotation time setting input window, a suspend button and a pump sequence setting button.

5. The water supply system according to claim 1, characterized in that: The water supply system further includes a rate change limiter configured to limit excessive changes in control instructions of the first controller and the second controller to prevent fluctuations in the system.

6. The water supply system according to claim 1, characterized in that: The water supply module also includes: a high-pressure cylinder, a low-pressure cylinder, a condenser, a condensate pump, a low-pressure heater, a high-pressure heater and a deaerator.

7. The water supply system according to claim 1, characterized in that: The pump manual operation station is provided with a tracking module.

8. A control method for a water supply system of a multi-module high temperature gas-cooled reactor nuclear power plant as claimed in claims 1 to 7, characterized in that: The method comprises the following steps: (1) Determine the commissioning status of the nuclear island module First, the specific number of nuclear island modules to be put into operation in the reactor module needs to be determined according to the actual situation; (2) Start the feedwater pump according to the number of nuclear island modules put into operation By using the pump group selection controller and selecting the pump to be started according to the starting pump quantity demand information, current pump status information, sequence selection information executed by the sequence selection operation panel, etc., after the selection is completed, the start-up instruction of a specific pump is sent in combination with the pump status information and the water supply system operation requirements; (3) Adjust the water flow rate to meet the water supply needs of the corresponding nuclear island module By setting a first controller for controlling the water supply main pipe pressure of the steam generator inlet of each nuclear island module at a set value and a second controller for controlling the water supply flow rate of the steam generator inlet of each nuclear island module to meet the water supply flow rate demand corresponding to the power of each nuclear island module, and a rate change limiter for collecting the larger value of the output of the first controller and the second controller, so as to limit the fluctuation of the system caused by excessive changes in the control instructions, after the setting is completed, multiple variable frequency feed water pumps are controlled by the first controller and the second controller according to the realization of the pump group control function to meet the larger value of the steam generator inlet main pipe pressure of each reactor module and the total demand of the steam generator inlet flow of each reactor module, so as to ensure that the output of the feed water system meets the water supply demand of the commissioned reactor module.

9. The control method according to claim 8, characterized in that: The step (2) further comprises the following sub-steps: The water supply pumps in the water supply system are sequenced. The sequence selection operation starts according to the current initial state of the operation panel. Click on the point control units in the control panel matrix in the order to be set. For example, you can first select the pump role of sequence 2 as pump C, or you can first select pump B in sequence 1. When a point control unit is selected, the column unit and row unit of the corresponding matrix are automatically invalidated. Next, you can still select the required units from the remaining valid point control units in the required order. The point control unit selected for the second time again makes the corresponding column remaining valid units and the corresponding row remaining valid units automatically invalid. After the point control unit is selected for the third time according to the rules, the automatic invalidation function is executed again. At this point, there will be only one valid point control unit in the sequence selection operation panel matrix, which will be automatically set to the selected state.

10. The control method according to claim 7, characterized in that: The control method also includes a manual operation mode, which is implemented by the pump manual operation station through its components and a matching tracking module, and the tracking module is configured to include a single pump manual operation station tracking function and a pump group manual operation station tracking function.