阅读说明：本技术 核电站rgl系统控制棒组控制方法 (Control method for nuclear power station RGL system control rod group ) 是由 曾晓华 于 2020-11-23 设计创作，主要内容包括：本发明涉及核电站棒控系统技术领域,具体涉及一种核电站RGL系统控制棒组控制方法。所述方法包括：在RGL试验过程中,若监测到逻辑柜出现故障而导致控制棒组处于非要求棒位时,将控制板快速提插装置安装至RGL系统中与所述电源柜通信连接,通过控制板快速提插装置控制电源柜解除控制棒组的移动闭锁状态；通过控制板快速提插装置向电源柜发送控制指令,令电源柜控制与故障机架对应的控制棒组移动至要求棒位,以消除发电机组的第一组I0,进而规避了发电机组的后撤的限制行为,避免了经济损失,减少了机组损耗及人力消耗；同时,本发明使得核电站操作人员有充分时间根除RGL系统的故障,减小了由于时间压力导致的人因失误。(The invention relates to the technical field of rod control systems of nuclear power plants, in particular to a control method of a rod group of an RGL system of a nuclear power plant. The method comprises the following steps: in the RGL test process, if the control rod group is in a non-required rod position due to the fact that the logic cabinet breaks down is monitored, the control panel quick plugging device is installed in the RGL system and is in communication connection with the power supply cabinet, and the power supply cabinet is controlled to release the moving locking state of the control rod group through the control panel quick plugging device; the control instruction is sent to the power cabinet through the quick control panel plugging device, and the power cabinet controls the control rod group corresponding to the fault rack to move to the required rod position, so that the first group I0 of the generator set is eliminated, the limitation action of the backward withdrawing of the generator set is avoided, the economic loss is avoided, and the unit loss and the labor consumption are reduced; meanwhile, the invention ensures that the operators of the nuclear power station have sufficient time to eradicate the fault of the RGL system, thereby reducing human errors caused by time pressure.)

1. A control method for a nuclear power plant RGL system control rod group is characterized by comprising the following steps:

in the RGL test process, if the control rod group of the generator set is monitored to be in a moving locking state corresponding to an unclaimed rod position, recording a first group I0 of the generator set, and judging whether a logic cabinet of an RGL system breaks down or not;

determining a fault rack in a logic cabinet of an RGL system through a power cabinet of the RGL system when the logic cabinet is confirmed to be in fault; the logic cabinet is in communication connection with the power supply cabinet; the power supply cabinet is electrically connected with all control rod groups in the RGL system; the fault rack is a UPAT rack or/and a UPP rack contained in the logic cabinet;

installing a control panel quick-plugging device into the RGL system so as to enable the control panel quick-plugging device to be in communication connection with the power cabinet, and further controlling the power cabinet to release the movement locking state of the control rod group through the control panel quick-plugging device;

and sending a control command to the power cabinet through the control panel quick plugging device, and enabling the power cabinet to execute a plugging event contained in the control command, so that the control rod group corresponding to the fault rack is controlled to move to a required rod position, and the first group I0 of the generator set is eliminated.

2. The nuclear power plant RGL system control stick group control method of claim 1, wherein said determining, by a power supply cabinet of the RGL system, a failed rack in the logic cabinet comprises:

and when detecting that the control rod group which is controlled to be in a moving locking state under the power cabinet is a shutdown rod group or a temperature rod group, determining that the fault rack is a UPAT rack.

3. The nuclear power plant RGL system control stick group control method of claim 1, wherein said determining, by a power supply cabinet of the RGL system, a failed rack in the logic cabinet comprises:

and when detecting that the control rod group which is controlled to be in a moving locking state under the power cabinet is a power rod group, determining that the fault rack is a UPP rack.

4. The nuclear power plant RGL system control rod set control method of claim 1, wherein the control board quick-plugging means comprises a user terminal, a data acquisition device connected between the user terminal and the power cabinet, and a level conversion device connected between the data acquisition device and the RGL system; the user terminal is used for displaying a human-computer interaction interface for nuclear power station operators to enter control instructions; the data acquisition equipment is used for sending the control instruction to the power supply cabinet; the level conversion device is used for converting the level of the data acquisition device into the logic level of the RGL system.

5. The method for controlling the rod group of the nuclear power plant RGL system of claim 4, wherein the control board quick-plugging device further comprises a bus interface clip connected with the level shifting device; the fault rack comprises a control card which is in communication connection with a CPU board card of the fault rack;

the installing the control panel quick lifting and inserting device into the RGL system comprises the following steps:

and controlling the control clamping piece to withdraw from the fault rack, inserting the control panel quick lifting and inserting device into the fault rack through the bus interface clamping piece so as to enable the control panel quick lifting and inserting device to be in communication connection with the power cabinet corresponding to the fault rack through the fault rack, and further indicating the power cabinet connected with the control panel quick lifting and inserting device to control the control rod group corresponding to the fault rack through a control instruction input from the human-computer interaction interface.

6. The nuclear power plant RGL system control rod set control method of claim 4, wherein said causing said power supply cabinet to execute a plug-in event contained in said control instructions comprises:

enabling the power supply cabinet to obtain a parameter variable contained in the control command, wherein the parameter variable is determined according to the current non-required rod position of the control rod group corresponding to the fault rack and the required rod position;

and enabling the power supply cabinet to determine a moving rod time sequence according to the parameter variable, and further controlling a control rod group corresponding to the fault rack to execute the lifting and inserting event according to the moving rod time sequence.

7. The method of nuclear power plant RGL system control rod set control according to claim 4, wherein said causing said power supply cabinet to obtain the parameter variables included in said control command further comprises:

sending a parameter variable modification instruction containing a variable value to be modified to the power supply cabinet through the control panel quick plug-in device, and recording the variable value to be modified as a new parameter variable corresponding to the plug-in event; the parameter variable modification instruction is generated after a nuclear power plant operator inputs a variable value to be modified in a human-computer interaction interface and triggers a parameter sending button;

and enabling the power supply cabinet to determine a new moving rod time sequence according to the new parameter variable, and further controlling a control rod group corresponding to the fault rack to execute the lifting and inserting event according to the new moving rod time sequence.

8. The method of controlling a nuclear power plant RGL system control rod set according to claim 4, wherein the installing the control board quick-lifting device into the RGL system to communicatively connect the control board quick-lifting device with the power cabinet, and further after controlling the power cabinet to release the movement locking state of the control rod set by the control board quick-lifting device, further comprises:

and when the power supply cabinet does not receive the control instruction sent by the control panel rapid plugging device within the preset time length, the power supply cabinet executes an overtime event to send an overtime fault alarm to a preset fault processing party.

9. The method for controlling the RGL system control rod set in the nuclear power plant as claimed in claim 4, wherein the controlling the power supply cabinet to release the movement locking state of the control rod set by the control board quick-plugging device includes:

sending a fault clearing instruction to the power cabinet through the control panel quick plug-in device, wherein the fault clearing instruction is generated after a nuclear power station operator triggers a fault clearing button in a man-machine interaction interface;

and enabling the power supply cabinet to execute the fault clearing event contained in the fault clearing instruction so as to release the movement locking state of the control rod group.

10. The nuclear power plant RGL system control stick group control method of claim 4, wherein said communicatively coupling said control board quick-connect and quick-disconnect device to said power supply cabinet comprises:

when an operator of the nuclear power station triggers an operation button in a man-machine interaction interface, the data acquisition equipment and the level conversion equipment are controlled to operate, and communication connection between the control panel quick plugging device and the power cabinet is established.

11. The method of nuclear power plant RGL system control stick set control of claim 10, wherein after said communicatively coupling said control board quick-connect device to said power cabinet, further comprising:

when an operator of the nuclear power station triggers a shutdown button in a man-machine interaction interface, the data acquisition equipment and the level conversion equipment are controlled to stop running, and the communication connection between the control panel quick plugging device and the power cabinet is disconnected.

12. The method for controlling the RGL system control rod group of the nuclear power plant as claimed in claim 1, wherein the determining whether the logic cabinet of the RGL system has a fault comprises:

when a power cabinet of an RGL system is confirmed to be in fault, a first LCS rack in the power cabinet in fault is determined, the first LCS rack is replaced by a second LCS rack in the RGL test environment, the type of the second LCS rack is consistent with that of the first LCS rack, and then the logic cabinet controls the control rod group to move from a non-required rod position to a required rod position through the power cabinet; the second LCS framework belongs to the same type of other power cabinets in the RGL trial environment as the failed power cabinet.

Technical Field

The invention relates to the technical field of rod control systems of nuclear power plants, in particular to a control method of a rod group of an RGL system of a nuclear power plant.

Background

The generator sets in a nuclear power plant are required to position control rod groups in the reactor core in different states, for example, each control rod group requires 225 steps during daily full power operation; in the RGL (rod control rod position system) test process, nuclear power station operating personnel need to protect the whole test process, because the RGL system trouble leads to the control rod group not when requiring the rod position, the generating set will withdraw after 1 hour, and the generating set can begin to reduce power according to the regulation this moment, and the generated energy reduces promptly, can cause very big economic loss and certain equipment damage. Therefore, how to complete fault handling and lift the control rod group to the required rod position within 1 hour so as to avoid the immeasurable loss caused by the withdrawal of the generator set is an important problem to be solved currently.

In the prior art, a nuclear power plant operator of a nuclear power plant usually checks and records an RGL system fault phenomenon, further performs detailed fault troubleshooting according to experience, determines what the fault reason is, and further performs a solution for the fault reason, wherein all the processes are required to be completed within one hour so as to restore the normal operation of the system before the generator set is withdrawn.

However, according to the conventional fault handling experience, the time margin of the fault handling process in the RGL test process is very small, especially for the logic cabinet of the RGL system, the time pressure on the nuclear power plant operator is quite huge, and the fault handling under the pressure can increase the probability of human error caused by time pressure, so that the possibility of economic loss caused by withdrawing a generator set is increased, and meanwhile, the unit loss and the human consumption of the scheme of the terminal in the prior art are large.

Disclosure of Invention

The embodiment of the invention provides a control rod group control method for an RGL system of a nuclear power station, which solves the problem that when a logic cabinet of the RGL system breaks down, a control rod group cannot be timely lifted back to a required rod position, so that a generator set is possibly withdrawn.

A control method for a nuclear power plant RGL system control rod group comprises the following steps:

in the RGL test process, if the control rod group of the generator set is monitored to be in a moving locking state corresponding to an unclaimed rod position, recording a first group I0 of the generator set, and judging whether a logic cabinet of an RGL system breaks down or not;

determining a fault rack in a logic cabinet of an RGL system through a power cabinet of the RGL system when the logic cabinet is confirmed to be in fault; the logic cabinet is in communication connection with the power supply cabinet; the power supply cabinet is electrically connected with all control rod groups in the RGL system; the fault rack is a UPAT rack or/and a UPP rack contained in the logic cabinet;

installing a control panel quick-plugging device into the RGL system so as to enable the control panel quick-plugging device to be in communication connection with the power cabinet, and further controlling the power cabinet to release the movement locking state of the control rod group through the control panel quick-plugging device;

and sending a control command to the power cabinet through the control panel quick plugging device, and enabling the power cabinet to execute a plugging event contained in the control command, so that the control rod group corresponding to the fault rack is controlled to move to a required rod position, and the first group I0 of the generator set is eliminated.

Optionally, the determining, by a power cabinet of the RGL system, a failed chassis in the logic cabinet comprises:

and when detecting that the control rod group which is controlled to be in a moving locking state under the power cabinet is a shutdown rod group or a temperature rod group, determining that the fault rack is a UPAT rack.

Optionally, the determining, by a power cabinet of the RGL system, a failed chassis in the logic cabinet comprises:

and when detecting that the control rod group which is controlled to be in a moving locking state under the power cabinet is a power rod group, determining that the fault rack is a UPP rack.

Optionally, the control panel rapid lifting and inserting device comprises a user terminal, a data acquisition device connected between the user terminal and the power supply cabinet, and a level conversion device connected between the data acquisition device and the RGL system; the user terminal is used for displaying a human-computer interaction interface for nuclear power station operators to enter control instructions; the data acquisition equipment is used for sending the control instruction to the power supply cabinet; the level conversion device is used for converting the level of the data acquisition device into the logic level of the RGL system.

Optionally, the control panel quick plugging device further comprises a bus interface card connected with the level conversion equipment; the fault rack comprises a control card which is in communication connection with a CPU board card of the fault rack;

the installing the control panel quick lifting and inserting device into the RGL system comprises the following steps:

and controlling the control clamping piece to withdraw from the fault rack, inserting the control panel quick lifting and inserting device into the fault rack through the bus interface clamping piece so as to enable the control panel quick lifting and inserting device to be in communication connection with the power cabinet corresponding to the fault rack through the fault rack, and further indicating the power cabinet connected with the control panel quick lifting and inserting device to control the control rod group corresponding to the fault rack through a control instruction input from the human-computer interaction interface.

Optionally, the causing the power supply cabinet to execute a plug-in event included in the control instruction includes:

enabling the power supply cabinet to obtain a parameter variable contained in the control command, wherein the parameter variable is determined according to the current non-required rod position of the control rod group corresponding to the fault rack and the required rod position;

and enabling the power supply cabinet to determine a moving rod time sequence according to the parameter variable, and further controlling a control rod group corresponding to the fault rack to execute the lifting and inserting event according to the moving rod time sequence.

Optionally, after the instructing the power supply cabinet to obtain the parameter variable included in the control instruction, the method further includes:

sending a parameter variable modification instruction containing a variable value to be modified to the power supply cabinet through the control panel quick plug-in device, and recording the variable value to be modified as a new parameter variable corresponding to the plug-in event; the parameter variable modification instruction is generated after a nuclear power plant operator inputs a variable value to be modified in a human-computer interaction interface and triggers a parameter sending button;

and enabling the power supply cabinet to determine a new moving rod time sequence according to the new parameter variable, and further controlling a control rod group corresponding to the fault rack to execute the lifting and inserting event according to the new moving rod time sequence.

Optionally, after the installing the control board quick-plug device into the RGL system to enable the control board quick-plug device to be in communication connection with the power supply cabinet, and further controlling the power supply cabinet to release the movement locking state of the control rod group through the control board quick-plug device, the method further includes:

and when the power supply cabinet does not receive the control instruction sent by the control panel rapid plugging device within the preset time length, the power supply cabinet executes an overtime event to send an overtime fault alarm to a preset fault processing party.

Optionally, the controlling the power cabinet to release the movement locking state of the control rod group by the control panel quick-plug device includes:

sending a fault clearing instruction to the power cabinet through the control panel quick plug-in device, wherein the fault clearing instruction is generated after a nuclear power station operator triggers a fault clearing button in a man-machine interaction interface;

and enabling the power supply cabinet to execute the fault clearing event contained in the fault clearing instruction so as to release the movement locking state of the control rod group.

Optionally, the enabling the quick control panel lifting and inserting device to be in communication connection with the power supply cabinet includes:

when an operator of the nuclear power station triggers an operation button in a man-machine interaction interface, the data acquisition equipment and the level conversion equipment are controlled to operate, and communication connection between the control panel quick plugging device and the power cabinet is established.

Optionally, after the rapid control board plugging device is communicatively connected to the power cabinet, the method further includes:

when an operator of the nuclear power station triggers a shutdown button in a man-machine interaction interface, the data acquisition equipment and the level conversion equipment are controlled to stop running, and the communication connection between the control panel quick plugging device and the power cabinet is disconnected.

Optionally, after determining whether the logic cabinet of the RGL system fails, the method includes:

when a power cabinet of an RGL system is confirmed to be in fault, a first LCS rack in the power cabinet in fault is determined, the first LCS rack is replaced by a second LCS rack in the RGL test environment, the type of the second LCS rack is consistent with that of the first LCS rack, and then the logic cabinet controls the control rod group to move from a non-required rod position to a required rod position through the power cabinet; the second LCS framework belongs to the same type of other power cabinets in the RGL trial environment as the failed power cabinet.

The invention provides a control method of a nuclear power station RGL system control rod group, in the RGL test process, if the control rod group is in an unclaimed rod position due to the fact that a logic cabinet is in failure, in order to avoid the situation that a generator set is withdrawn due to the fact that failure processing is not timely (after the control rod group is not in the unclaimed rod position due to the failure of the RGL system and lasts for one hour, the generator set is withdrawn), the control rod group control method controls a control rod group corresponding to a failed rack to move to the unclaimed rod position by quickly inserting a control panel and quickly connecting with a power cabinet and removing the moving locking state of the control rod group, further sends a control command to the power cabinet by the quickly inserting device of the control panel, enables the power cabinet to execute an inserting event contained in the control command, thereby controlling the control rod group corresponding to the failed rack to move to the unclaimed rod position to eliminate a first group I0 of the generator, the time that the control rod group is in the non-required rod position cannot last for one hour, and the limitation action of backward movement of the generator set is avoided; the method provides larger fault processing time margin for on-site nuclear power station operators, greatly reduces the time pressure of the nuclear power station operators, reduces the possibility of human errors possibly caused by time pressure, enables the nuclear power station operators to have sufficient time to eradicate the faults of the RGL system, and simultaneously avoids economic loss to the greatest extent and reduces unit loss and manpower consumption.

Drawings

In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings used in the description of the embodiments of the present invention will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art that other drawings can be obtained based on these drawings without inventive labor.

FIG. 1 is a flow chart of a nuclear power plant RGL system control rod set control method in accordance with an embodiment of the present invention;

fig. 2 is a schematic structural diagram of an RGL system and a control board quick-lifting device according to an embodiment of the present invention.

Fig. 3 is a schematic structural diagram of an RGL system and a control board quick-lifting device according to another embodiment of the present invention.

FIG. 4 is a schematic diagram of a human-machine interface of a control panel quick-loading device according to another embodiment of the present invention.

The reference numerals in the specification are as follows:

1. a logic cabinet; 11. a UPAT frame; 12. a UPP rack; 2. a power supply cabinet; 21. an LCS frame; 3. The control panel is quickly lifted and inserted into the device; 31. a user terminal; 32. a data acquisition device; 33. a level shifting device; 34. a bus interface card; 4. and (4) controlling the rod set.

Detailed Description

The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, 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 protection scope of the present invention.

The method for controlling the nuclear power plant RGL system control rod group 4 provided by the invention comprises the following steps as shown in figures 1 to 3:

s10, in the RGL test process, if the control rod group 4 of the generator set is monitored to be in a moving locking state corresponding to the non-required rod position, recording the first group I0 of the generator set, and judging whether the logic cabinet 1 of the RGL system has a fault or not; understandably, during the performance of an RGL (rod position system) test, the plant operator manually advances 10 steps after inserting 10 steps each control rod set 4 one by one and then returns to 225 steps. If the RGL system fails in this process, the control rod group 4 cannot move and is stuck in a non-required rod position (the required rod position is 225 steps, and the non-required rod position is a rod position other than 225), at this time, the generator set records the first group I0, if the control rod group 4 is not lifted to the required rod position within one hour, the generator set starts to reduce power according to the regulation at this time, that is, the power generation amount is reduced, and great economic loss and certain equipment damage are caused. Understandably, as shown in fig. 2 to 3, the control rod sets 4 of the RGL system are controlled by the power supply cabinet 2, the power supply cabinet 2 controls the movement of each control rod set 4 according to a control command received from a UPAT (shutdown temperature rod logic unit) rack 11 or a UPP (power rod logic processing and reactor power calculation unit) rack 12 of the logic cabinet 1, and when the UPAT rack 11 or the UPP rack 12 in the logic cabinet 1 fails to interact with the power supply cabinet 2, the power supply cabinet 2 cannot control the movement of the control rod set 4 and is in a movement locking state, so that the control rod set 4 is in a non-required rod position. Meanwhile, when the power cabinet 2 fails, the control rod set 4 is also in a movement locking state and cannot move, so that the control rod set 4 is in a non-required rod position. Therefore, when the control rod group 4 of the generator set is monitored to be in the movement locking state corresponding to the non-required rod position and the non-required rod position, the generator set firstly records the first group I0, at this time, it is required to firstly determine whether the fault reason of the RGL system is the fault of the power cabinet 2 or the fault of the logic cabinet 1, and then correspondingly process the fault, so as to release the first group I0 of the generator set. The power cabinet 2 includes an LCS (logical processing unit of the power cabinet 2 for implementing logical processing function) rack. Understandably, the UPAT chassis 11 and the UPP chassis 12 in the logic cabinet 1 respectively perform information interaction with the LCS chassis 21 of the power cabinet 2 through respective inter-cabinet data buses. The UPAT rack 11, the UPP rack 12 and the LCS rack 21 are all formed by combining a plurality of independent boards into a whole with a certain specific function, and the cabinets (the logic cabinet 1 and the power cabinet 2) are formed by a plurality of layers of racks which realize different functions and can be drawn out of and pushed into the cabinets.

S20, when confirming that logic cabinet 1 of RGL system is failed, determining the failed rack in the logic cabinet 1 through the power cabinet 2 of the RGL system; the logic cabinet 1 is in communication connection with the power supply cabinet 2; the power supply cabinet 2 is electrically connected with all the control rod groups 4 in the RGL system; the failure rack is a UPAT rack 11 or/and a UPP rack 12 contained in the logic cabinet 1. That is, when it is confirmed that the logic cabinet 1 of the RGL system has a fault, the fault rack may be the UPAT rack 11 or the UPP rack 12, since different control rod sets 4 are controlled by different racks in the logic cabinet 1, when the control rod set 4 in the movement locking state is known, the fault rack corresponding to the control rod set can be correspondingly determined, and the determination process can be performed by the power cabinet 2. In the normal RGL test process, the power supply cabinet 2 will detect the control command (or other signals such as a waiting signal) sent by the UPAT rack 11 or the UPP rack 12 at regular time to confirm that the two racks 11 or 12 are operating normally; when the power supply cabinet 2 does not receive the control command sent by the UPAT rack 11 and the UPP rack 12 (i.e., the faulty rack) at a certain timing, the power supply cabinet 2 will control the control rod set 4 corresponding to the faulty rack to be in the movement locking state, so that the power supply cabinet 2 can determine that the faulty rack is the UPAT rack 11 or/and the UPP rack 12 (i.e., the power supply cabinet 2 does not receive the control command or signal sent by the faulty rack at a certain timing).

Optionally, in step S20, determining a failed rack in the logic cabinet 1 through the power cabinet 2 of the RGL system includes: when the control rod group 4 controlled to be in the moving locking state under the power cabinet 2 is detected to be a shutdown rod group or a temperature rod group, the fault rack is determined to be the UPAT rack 11. The different control rod groups 4 are controlled by different racks in the logic cabinet 1, and when the control rod group 4 in the moving locking state is determined to be a shutdown rod group or a temperature rod group, the fault rack is a UPAT rack 11 for controlling the shutdown rod group and the temperature rod group. In the human-computer interaction interface shown in fig. 4, SA1, SA2, SB1, SB2, SC, SD1 and SD2 are shutdown rod groups; r1 and R2 are temperature bar groups. When the fault rack is determined to be the UPAT rack 11, the UPAT rack 11 can be selected in the man-machine interaction interface through the selection rod in the figure 4, and then different temperature rod groups or shutdown rod groups are selected in the man-machine interaction interface to be controlled.

Optionally, in step S20, determining a failed rack in the logic cabinet 1 through the power cabinet 2 of the RGL system includes: when the control rod set 4 controlled to be in the moving locking state under the power cabinet 2 is detected to be a power rod set, the fault rack is determined to be the UPP rack 12. Similarly, since different control bar sets 4 are controlled by different racks in the logic cabinet 1, when the control bar set 4 in the moving lockout state is determined to be a power bar set, the malfunctioning rack is the UPP rack 12 for controlling the power bar set. In the human-computer interface shown in fig. 4, G1, G21, G21, N11, N12, N21, and N22 are all power bar groups. When the faulty rack is determined to be a UPP rack 12, the UPP rack 12 may be selected in the human machine interface by the selection lever in fig. 4, and then a different power bar group is selected in the human machine interface to be controlled.

S30, installing the control board quick-lifting-inserting device 3 into the RGL system, so that the control board quick-lifting-inserting device 3 is in communication connection with the power cabinet 2, and the power cabinet 2 is controlled by the control board quick-lifting-inserting device 3 to release the movement locking state of the control rod group 4; after the movement lock state of the control stick set 4 is released, the control stick set 4 can be moved. Understandably, after the control board rapid plugging device 3 is in communication connection with the power supply cabinet 2, different parameter variables may be set for different control bar groups 4 according to the currently located non-required bar position of the control bar group 4, where the parameter variables represent the to-be-corrected amount of the phase difference between the current non-required bar position and the required bar position (the parameter variables may be equal to the number of deviation steps between the control bar group 4 and the required bar position), and then each plugging action may be executed according to the parameter variables when a plugging event is executed.

Optionally, the control panel quick-lifting device 3 comprises a user terminal 31, a data acquisition device 32 connected between the user terminal 31 and the power supply cabinet 2, and a level conversion device 33 connected between the data acquisition device 32 and the RGL system; the user terminal 31 is used for displaying a human-computer interaction interface for nuclear power station operators to enter control instructions; the data acquisition device 32 is configured to send the control instruction to the power supply cabinet 2; the level translation device 33 is used to translate the level of the data acquisition device 32 to the logic level of the RGL system. That is, the user terminal 31 may be a computer terminal device such as a notebook computer, a pad, a mobile phone, and a desktop, and the user terminal 31 may operate the human-computer interaction interface, and then trigger a control instruction including a plug-in event, a fault clearing instruction, a parameter variable modification instruction, and the like in the human-computer interaction interface (displayed by a human-computer interaction program). The data acquisition device 32(NI) can communicate with the human-computer interaction program, and then finally transmit the generated instructions and the like to the power cabinet 2; the level shifting device 33 is used to effect a shift of the logic levels of the data acquisition device 32 and the RGL system.

Further, the control board quick-insertion device 3 further comprises a bus interface clamping piece 34 connected with the level conversion device 33, and the bus interface clamping piece 34 can realize quick butt joint of the control board quick-insertion device 3 and the RGL system. The fault rack comprises a control card which is in communication connection with a CPU board card of the fault rack; when a fault rack of the logic cabinet 1 breaks down, the control clamping piece withdraws from the fault rack, the control panel quick plug-in device 3 is plugged into the fault rack through the bus interface clamping piece 34, so that the control panel quick plug-in device 3 is in communication connection with the power cabinet 2 corresponding to the fault rack through the fault rack, and the power cabinet 2 connected with the control panel quick plug-in device 3 is indicated to control the control rod group 4 corresponding to the fault rack through a control instruction recorded from the human-computer interaction interface.

The control board rapid lifting and inserting device 3 can be used as an additional newly-added off-line device in the RGL system, is not accessed under the normal operation condition of the RGL system, and is only rapidly inserted and used under the condition that a fault rack exists in the logic cabinet 1 of the RGL system, so that the use convenience is improved. The control panel rapid plug-in device 3 can replace a communication protocol between a fault rack of the original logic cabinet 1 and the power supply cabinet 2. And a human-computer interaction program with a human-computer interaction interface is arranged, the display content and logic of each part of the human-computer interaction interface are clear, the operation and the control can be convenient, the human-factor prevention engineering can be considered, and the human-computer interaction error is avoided.

Understandably, as shown in fig. 4, the human-computer interface can select the modes of correction 1 and correction 2, and then the control board quick-plugging device 3 can communicate with the power cabinet 2 in one of the modes to control the control rod set 4. Wherein, in the correction 1 mode: any one of the rod sets (shutdown, temperature or power) may be selected to control the step-out correction of the selected rod set or/and meet certain experimental requirements. In calibration 1 mode, the corresponding bar position counter of the selected bar set is controlled to be unchanged, and the number of lifting steps of each bar set is counted by a dedicated bar position counter (as shown in fig. 4, the bar position counter is 015QM or 016QM of the RGL system shown in the figure, wherein 015QM corresponds to the shutdown temperature bar set, and 016QM corresponds to the power bar set). Secondly, when the inserting rod is lifted, two sub-rod groups of the same rod group move simultaneously; again, in calibration 1 mode, the temperature bar set and power bar set can be freely interpolated between 5 steps and 225 steps, but the power bars do not follow an iterative procedure, i.e., each bar set of the power bar set can operate independently.

While in correction 2 mode: any one of the bar sets (shutdown bar set, temperature bar set, or power bar set) may be selected for controlling the correction of the loss of synchronism of the bar set 4 or/and to meet the requirements of certain experiments. In the calibration 2 mode, first, the rod position counter of the control rod group 4 will change following the actual number of insertion steps, i.e. the dedicated rod position counter corresponding to the selected rod group starts counting; secondly, when the inserting rod is lifted, the two sub-rod groups of the same rod group move in half step; third, in calibration 2 mode, the power bar sets follow an iterative procedure, i.e., the number of insertion steps of each bar set of the power bar sets is linked.

Understandably, the two subgroup positions of the same stick group are the same under normal conditions, i.e. the number of steps is the same, and due to the fault, the control stick group 4 corresponding to the fault rack may be out of step during the movement; that is, the rod position deviation (deviation means deviation in the number of moving steps) of different subgroups needs to be corrected by the two correction modes so that the two subgroups are at the same rod position, for example, there may be a case where the subgroup 1 is at 220 steps and the subgroup 2 is at 119 steps.

Optionally, the control board quick-lifting and inserting device 3 further comprises a bus interface clamping piece 34 connected with the level conversion equipment 33; the fault rack comprises a control card which is in communication connection with a CPU board card of the fault rack; the control panel rapid lifting and inserting device 3 can be used as an extra newly-added off-line device in an RGL system, is not connected under the normal operation condition of the RGL system, is rapidly inserted and used through the bus interface clamping piece 34 only under the condition that a fault rack exists in a logic cabinet 1 of the RGL system, and improves the use convenience.

Further, in step S30, installing the control board quick-lifting device 3 into the RGL system includes:

and controlling the control clamping piece to withdraw from the fault rack, inserting the control panel quick plug-in device 3 into the fault rack through the bus interface clamping piece 34 so as to enable the control panel quick plug-in device 3 to be in communication connection with the power cabinet 2 corresponding to the fault rack through the fault rack, and further indicating the power cabinet 2 connected with the control panel quick plug-in device 3 to control the control rod group 4 corresponding to the fault rack through a control instruction recorded from the human-computer interaction interface.

That is, the bus interface fastener 34 is a bus access tool dedicated to the control board quick-insertion device 3, so that the access and use of the control board quick-insertion device 3 become more convenient and quicker; the shape and structure of the bus interface card 34 are consistent with those of the control card (the control card is in communication connection with the CPU card of the fault rack), so that when the bus interface card 34 needs to be used, the bus interface card 34 is inserted into the position of the fault rack where the control card is originally inserted, and therefore, the control card needs to be pulled down when the bus interface card 34 is used; after the bus interface card 34 is inserted into the position of the original inserted control card in the fault rack, the control board quick-lifting device 3 is connected with the communication bus of the RGL system, and then the communication connection with the power supply cabinet 2 can be realized through the communication bus.

Optionally, in step S30, the connecting the control board quick-loading device 3 with the power cabinet 2 in communication includes: when an operator of the nuclear power station triggers an operation button in a man-machine interaction interface, the data acquisition equipment 32 and the level conversion equipment 33 are controlled to operate, and communication connection between the control panel quick plug-in device 3 and the power cabinet 2 is established. That is, in this step, only by clicking a "click operation" button (i.e., an operation button) on the human-computer interaction interface, the data acquisition device 32 and the level conversion device 33 can be controlled to operate, and the communication connection between the control board rapid insertion device 3 and the power supply cabinet 2 is established.

Optionally, in the step S30, after the control board quick-loading device 3 is communicatively connected to the power cabinet 2, the method further includes: when the nuclear power plant operator triggers a shutdown button in a human-computer interaction interface, the data acquisition equipment 32 and the level conversion equipment 33 are controlled to stop running, and the communication connection between the control panel quick plugging device 3 and the power cabinet 2 is disconnected. That is, in this step, only by clicking the "operation" button (i.e., the operation button) on the human-computer interaction interface, the "operation" button is changed to the "operation stop" button, and at this time, only by clicking the "operation stop" button, the data acquisition device 32 and the level conversion device 33 can be controlled to stop operating, so as to disconnect the communication connection between the control board quick plug-in device 3 and the power supply cabinet 2.

Optionally, in the step S30, the controlling, by the control board quick-lifting device 3, the power supply cabinet 2 to release the movement locking state of the control rod group 4 includes:

sending a fault clearing instruction to the power cabinet 2 through the control panel quick plug-in device 3, wherein the fault clearing instruction is generated after a nuclear power station operator triggers a fault clearing button in a man-machine interaction interface;

and enabling the power supply cabinet 2 to execute the fault clearing event contained in the fault clearing instruction so as to release the movement locking state of the control rod set 4.

That is, in this embodiment, only by clicking a "failure report" button (that is, a failure clearing button) on a human-computer interaction interface, a failure clearing instruction can be sent to the power cabinet 2, and then the power cabinet 2 is made to execute a failure clearing event included in the failure clearing instruction to release the movement locking state of the control rod group 4, and then a control instruction can be sent to the power cabinet 2 through the control board fast plugging device 3, and the power cabinet 2 is made to execute a plugging event included in the control instruction, so that the control rod group 4 corresponding to the failed rack is controlled to move to a required rod position. Before the control panel rapid plugging device 3 sends a fault clearing instruction to the power cabinet 2, the control rod group 4 corresponding to the fault rack is always in a moving locking state and cannot move.

Optionally, after step S30, the method further includes: and when the power cabinet 2 does not receive the control instruction sent by the control panel rapid plug-in device 3 within the preset time length, the power cabinet 2 is made to execute an overtime event to send an overtime fault alarm to a preset fault handler. In this embodiment, if the user does not operate in the human-computer interaction interface for a long time, the human-computer interaction software may send a control instruction including the waiting information to the power cabinet 2 at regular time (the time interval does not exceed the preset time), and in this embodiment, if the power cabinet 2 does not receive any control instruction after exceeding the preset time (for example, 6 seconds), the timeout event may be executed to send a timeout fault alarm to the preset fault handler, so that the preset fault handler performs alarm processing according to the timeout fault alarm.

And S40, sending a control command to the power cabinet 2 through the control panel quick plug-in device 3, and enabling the power cabinet 2 to execute a plug-in event contained in the control command, so as to control the control rod group 4 corresponding to the fault rack to move to a required rod position, thereby eliminating the first group I0 of the generator set.

That is, when the required position is 225 steps, the step S40 may finally make the control stick set 4 corresponding to the failed rack go back to 225 steps to eliminate the first set I0 of the genset, and avoid the genset from being pulled back because the control stick set 4 does not last for one hour at the required position. After step S40, the nuclear power plant operator needs to find the cause of the fault of the faulty rack and eliminate the cause of the fault as soon as possible, and after the fault of the faulty rack is eliminated, the bus interface card 34 of the control board quick-insertion device 3 can be pulled out, the control card can be reinserted to connect the control card with the CPU card of the faulty rack in a communication manner, and then the faulty rack (no fault exists) which has recovered to be normal is made to control the corresponding control rod group 4 through the power cabinet 2.

Optionally, in step S40, the causing the power cabinet 2 to execute the plug-in event included in the control command includes:

enabling the power supply cabinet 2 to obtain a parameter variable contained in the control instruction, wherein the parameter variable is determined according to the current non-required rod position and the required rod position of the control rod group 4 corresponding to the fault rack;

and enabling the power supply cabinet 2 to determine a moving rod time sequence according to the parameter variable, and further controlling a control rod group 4 corresponding to the fault rack to execute the lifting and inserting event according to the moving rod time sequence.

Understandably, the moving rod time sequence is formed by arranging different numbers of step-up events and step-down events according to a preset sequence, and the moving rod time sequence is set by the power supply cabinet 2 according to parameter variables contained in the control instruction. And then, after the nuclear power station operator can check the display content correctly, the operator can click a step-up button (corresponding to the step-up event) or a step-in button (corresponding to the step-in event) on the human-computer interaction interface, and then the power cabinet 2 controls the control rod group 4 to execute the step-up event corresponding to the pressed button.

Specifically, when the plug-in event is a step-up event (a step-up event is triggered after a step-up button is triggered by a nuclear power plant operator in a human-computer interaction interface), the power supply cabinet 2 controls the control rod group 4 corresponding to the failed rack to perform a step-up operation on the basis of the current non-required rod position. And when the plug-in event is a one-step plug-in event (a one-step plug-in event is triggered after a one-step plug-in button is triggered in a man-machine interaction interface by a nuclear power station operator), the power cabinet 2 controls the control rod group 4 corresponding to the fault rack to plug in one step on the basis of the current non-required rod position.

Optionally, after the instructing the power cabinet 2 to obtain the parameter variable included in the control instruction, the method further includes:

sending a parameter variable modification instruction containing a variable value to be modified to the power cabinet 2 through the control panel rapid plug-in device 3, and recording the variable value to be modified as a new parameter variable corresponding to the plug-in event; the parameter variable modification instruction is generated after a nuclear power plant operator inputs a variable value to be modified in a human-computer interaction interface and triggers a parameter sending button;

and enabling the power supply cabinet 2 to determine a new moving rod time sequence according to the new parameter variable, and further controlling the control rod group 4 corresponding to the fault rack to execute the lifting and inserting event according to the new moving rod time sequence.

That is, the parameter variable corresponding to the above mentioned insertion event may be modified by the nuclear power plant operator on the human-computer interaction interface according to the requirement, and only after the variable value to be modified is entered in the human-computer interaction interface and the parameter sending button is clicked, the parameter variable modification instruction including the variable value to be modified is sent to the power supply cabinet 2. In the process of executing the lifting and inserting event corresponding to one control instruction, the parameter variable is updated in real time due to the real-time change of the rod position of the control rod group 4.

The invention provides a control method of a nuclear power station RGL system control rod group 4, in the RGL test process, if the control rod group 4 is in an unclaimed rod position due to the fact that a logic cabinet 1 is detected to have a fault, in order to avoid the situation that a generator set is withdrawn due to the fact that fault processing is not timely (after the control rod group 4 is not in the unclaimed rod position due to the fault of the RGL system and lasts for one hour, the generator set is withdrawn), the control rod fast-inserting device 3 is used for fast inserting and being in communication connection with a power cabinet 2 and removing the moving locking state of the control rod group 4, and then the control rod fast-inserting device 3 is used for sending a control command to the power cabinet 2 to enable the power cabinet 2 to execute an inserting and extracting event contained in the control command, so that the control rod group 4 corresponding to a fault rack is controlled to move to the required rod position to eliminate a first group I0 of the generator set, and even if the control rod group 4 can, the time that the control rod group 4 is in the non-required rod position cannot last for one hour, and the limitation action of withdrawing the generator set is avoided; the method provides larger fault processing time margin for on-site nuclear power station operators, greatly reduces the time pressure of the nuclear power station operators, reduces the possibility of human errors possibly caused by time pressure, enables the nuclear power station operators to have sufficient time to eradicate the faults of the RGL system, and simultaneously avoids economic loss to the greatest extent and reduces unit loss and manpower consumption. At present, the control method for the control rod group 4 of the RGL system of the nuclear power station is successfully tested on the minimum platform of the assembled RGL system, and the function of moving the control rod group 4 to the required rod position under the condition that a logic cabinet 1 of the RGL system fails is realized.

Optionally, the step S10, after determining whether the logic cabinet 1 of the RGL system has a fault, includes:

when confirming that a power cabinet 2 of an RGL system has a fault, determining a first LCS rack 21 with the fault in the power cabinet 2, and replacing the first LCS rack 21 with a second LCS rack 21 with the same type in an RGL test environment, and then enabling the logic cabinet 1 to control the control rod group 4 to move from a non-required rod position to a required rod position through the power cabinet 2; the second LCS framework 21 belongs to the other power cabinets 2 of the same type as the failed power cabinet 2 in the RGL trial environment. That is, in this embodiment, if a fault is caused by the power cabinet 2, at this time, the RGL test environment of the nuclear power plant usually has a plurality of completely identical power cabinets 2 (the RGL test environment of the nuclear power plant does not have a plurality of logic cabinets 1 of identical types, and therefore, the faulty rack in the logic cabinet 1 cannot be replaced in the same manner), so that the faulty first LCS rack 21 can be replaced by the second LCS rack 21, which is currently not used by the other power cabinets 2 in the RGL test environment and is identical to the power cabinet 2 in type (for example, in fig. 2, only one LCS rack 21 is used in both power cabinets 2, and at this time, the other LCS racks 21 not used in the power cabinet 2 at present can be used as the second LCS rack 21 to replace the faulty first LCS rack 21), so that the power cabinet 2 can quickly recover to a normal working state.

The above-mentioned embodiments are only used for illustrating the technical solutions of the present invention, and not for limiting the same; although the present invention has been described in detail with reference to the foregoing embodiments, it will be understood by those of ordinary skill in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some technical features may be equivalently replaced; such modifications and substitutions do not substantially depart from the spirit and scope of the embodiments of the present invention, and are intended to be included within the scope of the present invention.