Control Method of Control Rod Group in RGL System of Nuclear Power Plant

Abstract

The present invention relates to the technical field of rod control systems in nuclear power plants, and in particular to a control method for a control rod group of an RGL system in a nuclear power plant. The method comprises: during an RGL test, if a fault in a logic cabinet is detected, resulting in the control rod group being in a non-required rod position, installing a control panel quick insertion and extraction device in the RGL system and communicating with the power cabinet, controlling the power cabinet to release the movement locking state of the control rod group through the control panel quick insertion and extraction device; sending a control instruction to the power cabinet through the control panel quick insertion and extraction device, so that the power cabinet controls the control rod group corresponding to the faulty rack to move to the required rod position, so as to eliminate the first group I0 of the generator set, thereby avoiding the restricted behavior of the generator set's retreat, avoiding economic losses, and reducing unit losses and manpower consumption; at the same time, the present invention allows nuclear power plant operators to have sufficient time to eradicate the fault of the RGL system, reducing human errors caused by time pressure.

Description

Technical Field

[0001] The present invention relates to the technical field of rod control systems for nuclear power plants, and in particular to a control method for a control rod group of an RGL system in a nuclear power plant. Background Art

[0002] The generator sets in nuclear power plants have requirements for the position of the control rod group in the reactor core in different states. For example, during daily full-power operation, each group of control rods requires the rod position to be 225 steps; during the RGL (rod control rod position system) test, the nuclear power plant operators need to ensure the entire test process, because if the control rod group is not in the required position due to RGL system failure, the generator set will be withdrawn after 1 hour. At this time, the generator set will start to reduce power according to regulations, that is, the power generation will be reduced, which will cause great economic losses and certain equipment damage. Therefore, how to complete the fault handling within 1 hour and bring the control rod group back to the required rod position, thereby avoiding immeasurable losses caused by the withdrawal of the generator set, is an important issue that needs to be solved at present.

[0003] In the prior art, the nuclear power plant operators of the nuclear power plant usually verify and record the fault phenomenon of the RGL system, and then conduct detailed troubleshooting based on experience to determine the cause of the fault, and then implement solutions for the cause of the fault. The above process is required to be completed within one hour to restore the normal operation of the system before the generator set is withdrawn.

[0004] However, based on previous fault handling experience, the time margin of the fault handling process during the RGL test is very small, especially for the logic cabinet of the RGL system, which puts enormous time pressure on nuclear power plant operators. Fault handling under this pressure will increase the probability of human errors due to time constraints, and thus increase the possibility of economic losses due to the withdrawal of generator sets. At the same time, the above-mentioned solution of the prior art terminal has large unit losses and manpower consumption. Summary of the invention

[0005] The embodiment of the present invention provides a control rod group control method of an RGL system of a nuclear power plant. The present invention solves the problem that when a logic cabinet of the RGL system fails, the generator set may be retreated due to the control rod group failing to be brought back to the required rod position in time.

[0006] A control rod group control method for an RGL system of a nuclear power plant, comprising:

[0007] During the RGL test, if it is monitored that the control rod group of the generator set is in a moving locked state corresponding to a non-required rod position, the generator set is recorded as the first group I0, and it is determined whether the logic cabinet of the RGL system is faulty;

[0008] When it is confirmed that a logic cabinet of the RGL system fails, a faulty rack in the logic cabinet is determined through a power cabinet of the RGL system; the logic cabinet is communicatively connected with the power cabinet; the power cabinet is electrically connected with all control rod groups in the RGL system; the faulty rack is a UPAT rack or / and a UPP rack contained in the logic cabinet;

[0009] Installing a control panel quick lifting and insertion device into the RGL system so that the control panel quick lifting and insertion device is connected to the power cabinet for communication, and then controlling the power cabinet to release the movement locking state of the control rod group through the control panel quick lifting and insertion device;

[0010] A control instruction is sent to the power cabinet through the control panel quick lifting and insertion device, so that the power cabinet executes the lifting and insertion event contained in the control instruction, thereby controlling the control rod group corresponding to the faulty rack to move to the required rod position to eliminate the first group I0 of the generator set.

[0011] Optionally, determining the faulty rack in the logic cabinet through the power cabinet of the RGL system includes:

[0012] When it is detected that the control rod group under the power cabinet that is in the moving locked state is a shutdown rod group or a temperature rod group, it is determined that the faulty rack is a UPAT rack.

[0013] Optionally, determining the faulty rack in the logic cabinet through the power cabinet of the RGL system includes:

[0014] When it is detected that the control rod group in the movable locked state under the power cabinet is a power rod group, it is determined that the faulty rack is a UPP rack.

[0015] Optionally, the control panel quick lifting and insertion device includes 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 to display a human-computer interaction interface for nuclear power plant operators to enter control instructions; the data acquisition device is used to send the control instructions to the power supply cabinet; the level conversion device is used to convert the level of the data acquisition device into the logic level of the RGL system.

[0016] Optionally, the control board quick insertion and extraction device further comprises a bus interface card connected to the level conversion device; the faulty rack comprises a control card communicatively connected to the CPU board of the faulty rack;

[0017] The method of installing the control panel quick insertion and extraction device into the RGL system includes:

[0018] The control card is controlled to withdraw from the faulty rack, and the control panel quick lifting and insertion device is plugged into the faulty rack through the bus interface card, so that the control panel quick lifting and insertion device is communicated with the power cabinet corresponding to the faulty rack through the faulty rack, and then the power cabinet connected to the control panel quick lifting and insertion device is instructed to control the control rod group corresponding to the faulty rack through the control instructions entered from the human-computer interaction interface.

[0019] Optionally, the step of instructing the power cabinet to execute the lifting and inserting event contained in the control instruction includes:

[0020] Instructing the power supply cabinet to obtain a parameter variable included in the control instruction, wherein the parameter variable is determined according to a current non-required rod position and the required rod position of a control rod group corresponding to the faulty rack;

[0021] The power supply cabinet is instructed to determine a moving rod timing according to the parameter variable, and then control a control rod group corresponding to the faulty rack to execute the lifting and inserting event according to the moving rod timing.

[0022] Optionally, after instructing the power cabinet to obtain the parameter variable included in the control instruction, the method further includes:

[0023] Sending a parameter variable modification instruction containing the variable value to be modified to the power cabinet through the control panel quick insertion and lifting device, and recording the variable value to be modified as a new parameter variable corresponding to the insertion and lifting event; wherein the parameter variable modification instruction is generated after the nuclear power plant operator enters the variable value to be modified in the human-computer interaction interface and triggers the parameter sending button;

[0024] The power supply cabinet is instructed to determine a new moving rod timing according to the new parameter variable, and then control the control rod group corresponding to the faulty rack to execute the lifting and inserting event according to the new moving rod timing.

[0025] Optionally, after installing the control panel quick lifting and insertion device into the RGL system so that the control panel quick lifting and insertion device is connected to the power cabinet for communication, and then controlling the power cabinet to release the movement locking state of the control rod group through the control panel quick lifting and insertion device, the system further includes:

[0026] When the power cabinet does not receive the control instruction sent by the control panel quick lifting and plugging device within a preset time period, the power cabinet is made to execute a timeout event to send a timeout fault alarm to a preset fault processing party.

[0027] Optionally, controlling the power supply cabinet to release the movement locking state of the control rod group through the control panel quick lifting and inserting device includes:

[0028] Sending a fault clearing instruction to the power cabinet through the control panel quick lifting and inserting device, wherein the fault clearing instruction is generated after the nuclear power plant operator triggers the fault clearing button in the human-computer interaction interface;

[0029] The power supply cabinet is instructed to execute the fault clearing event contained in the fault clearing instruction to release the movement locking state of the control rod group.

[0030] Optionally, the control panel quick lifting and plugging device is communicatively connected with the power cabinet, comprising:

[0031] When the nuclear power plant operator triggers the run button in the human-machine interaction interface, the data acquisition device and the level conversion device are controlled to run, and a communication connection is established between the control panel quick lifting and plugging device and the power cabinet.

[0032] Optionally, after the control panel quick insertion and extraction device is communicatively connected with the power cabinet, the method further comprises:

[0033] When the nuclear power plant operator triggers the stop button in the human-machine interaction interface, the data acquisition device and the level conversion device are controlled to stop running, and the communication connection between the control panel quick lifting and plugging device and the power cabinet is disconnected.

[0034] Optionally, after determining whether a logic cabinet of the RGL system fails, the method further includes:

[0035] When it is confirmed that the power cabinet of the RGL system fails, the first LCS rack in the power cabinet where the failure occurs is determined, and after the first LCS rack is replaced with a second LCS rack of the same type in the RGL test environment, the logic cabinet controls the control rod group to move from the non-required rod position to the required rod position through the power cabinet; the second LCS rack belongs to other power cabinets of the same type as the failed power cabinet in the RGL test environment.

[0036] The control method for the control rod group of the RGL system of a nuclear power plant provided by the present invention, during the RGL test process, if it is monitored that a logic cabinet fails and the control rod group is in a non-required rod position, in order to avoid the generator set being withdrawn due to untimely fault handling (after the RGL system failure causes the control rod group to be out of the required rod position for one hour, the generator set will be withdrawn), the control panel quick lifting and insertion device quickly intervenes in the communication connection with the power cabinet and releases the movement locking state of the control rod group, and then sends a control instruction to the power cabinet through the control panel quick lifting and insertion device, so that the power cabinet executes the lifting and insertion event contained in the control instruction, thereby controlling the connection with the faulty machine The control rod group corresponding to the rack is moved to the required rod position to eliminate the first group I0 of the generator set, so that even if the control rod group can be restored to the required rod position in time, the time when the control rod group is in the non-required rod position cannot last for one hour, thereby avoiding the restricted behavior of the generator set's retreat; a larger fault handling time margin is provided to the on-site nuclear power plant operators, which greatly reduces the time pressure of the nuclear power plant operators and the possibility of human errors caused by time pressure, so that the nuclear power plant operators have sufficient time to eradicate the fault of the RGL system. At the same time, the present invention avoids economic losses to the greatest extent and reduces unit losses and manpower consumption. BRIEF DESCRIPTION OF THE DRAWINGS

[0037] In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the accompanying drawings required for use in the description of the embodiments of the present invention will be briefly introduced below. Obviously, the accompanying drawings in the following description are only some embodiments of the present invention. For ordinary technicians in this field, other accompanying drawings can be obtained based on these accompanying drawings without paying creative work.

[0038] Figure 1 is a flow chart of a control rod group control method of a nuclear power plant RGL system in one embodiment of the present invention;

[0039] Figure 2 It is a schematic diagram of the structure of the RGL system and the control panel quick lifting and insertion device in one embodiment of the present invention.

[0040] Figure 3 It is a schematic diagram of the structure of the RGL system and the control panel quick lifting and insertion device in another embodiment of the present invention.

[0041] Figure 4 It is a schematic diagram of a human-machine interaction interface of a control panel quick lifting and insertion device in another embodiment of the present invention.

[0042] The reference numerals in the specification are as follows:

[0043] 1. Logic cabinet; 11. UPAT rack; 12. UPP rack; 2. Power cabinet; 21. LCS rack; 3. Control board quick insertion and extraction device; 31. User terminal; 32. Data acquisition equipment; 33. Level conversion equipment; 34. Bus interface card; 4. Control rod assembly. DETAILED DESCRIPTION

[0044] The following will be combined with the drawings in the embodiments of the present invention to clearly and completely describe the technical solutions in the embodiments of the present invention. Obviously, the described embodiments are part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0045] The present invention provides a control method for the control rod group 4 of the RGL system of a nuclear power plant, such as Figures 1 to 3 As shown, the following steps are included:

[0046] S10, during the RGL test, if it is monitored that the control rod group 4 of the generator set is in a mobile locking state corresponding to a non-required rod position, the generator set will be recorded as the first group I0, and it will be determined whether the logic cabinet 1 of the RGL system has a fault; understandably, during the execution of the RGL (rod control rod position system) test, the nuclear power plant operator will manually insert each control rod group 4 one by one by 10 steps and then lift it up 10 steps back to 225 steps. If the RGL system fails during this process, it will cause the control rod group 4 to be unable to move and be stuck in a non-required rod position (the required rod position is 225 steps, and the non-required rod position is a rod position that is not 225). At this time, the generator set will be recorded as the first group I0. If the control rod group 4 is not lifted to the required rod position within one hour, the unit will begin to reduce power as required, that is, the power generation will be reduced, which will cause great economic losses and certain equipment damage. Understandably, if Figures 2 to 3As shown, the control rod group 4 of the RGL system is controlled by the power cabinet 2. The power cabinet 2 controls the movement of each control rod group 4 according to the control command received from the UPAT (shutdown temperature rod logic unit) rack 11 or the UPP (power rod logic processing and reactor power calculation unit) rack 12 of the logic cabinet 1. When the UPAT rack 11 or the UPP rack 12 in the logic cabinet 1 fails and cannot interact with the power cabinet 2, the power cabinet 2 cannot control the movement of the control rod group 4 and is in a movement locking state, thereby making the control rod group 4 in an unrequired rod position. At the same time, when the power cabinet 2 fails, the control rod group 4 will also be in a movement locking state and cannot move, thereby making the control rod group 4 in an unrequired rod position. Therefore, when it is monitored that the control rod group 4 of the generator set is in an unrequired rod position and a movement locking state corresponding to the unrequired rod position, the generator set will first record the first group I0. At this time, it is necessary to first determine whether the fault cause of the RGL system is the fault of the power cabinet 2 or the fault of the logic cabinet 1, and then perform corresponding processing on the fault, thereby releasing the first group I0 of the generator set. The power cabinet 2 includes an LCS (Logical Processing Unit of Power Cabinet 2, used to implement the logic processing function) rack. It can be understood that the UPAT rack 11 and the UPP rack 12 in the logic cabinet 1 exchange information with the LCS rack 21 of the power cabinet 2 through their respective inter-cabinet data buses. The UPAT rack 11, the UPP rack 12 and the LCS rack 21 are all multiple independent panels combined together to form a whole with a specific function. The cabinet (logic cabinet 1 and power cabinet 2) is composed of multiple layers of racks that implement different functions, and these racks can be pulled out and pushed in from the cabinet.

[0047] S20, when it is confirmed that the logic cabinet 1 of the RGL system fails, the faulty rack in the logic cabinet 1 is determined through the power cabinet 2 of the RGL system; the logic cabinet 1 is connected to the power cabinet 2 in communication; the power cabinet 2 is electrically connected to all control rod groups 4 in the RGL system; the faulty rack is the UPAT rack 11 and / or the UPP rack 12 contained in the logic cabinet 1. That is, when it is confirmed that the logic cabinet 1 of the RGL system fails, its faulty rack may be the UPAT rack 11 or the UPP rack 12. Since different control rod groups 4 are controlled by different racks in the logic cabinet 1, when the control rod group 4 in the mobile locking state is known, the corresponding faulty rack can also be determined accordingly, and the determination process can be performed by the power cabinet 2. During a normal RGL test, the power cabinet 2 will periodically detect the control command (or other signals such as waiting signal) sent by the UPAT rack 11 or the UPP rack 12 to confirm that the two racks UPAT rack 11 or the UPP rack 12 are operating normally; and when the power cabinet 2 does not periodically receive the control command sent by the UPAT rack 11 and the UPP rack 12 (that is, the faulty rack), the power cabinet 2 will control the control rod group 4 corresponding to the faulty rack to be in a moving locked state, so the power cabinet 2 can determine that the faulty rack is specifically the UPAT rack 11 and / or the UPP rack 12 (that is, the rack whose control command or signal the power cabinet 2 does not periodically receive).

[0048] Optionally, in step S20, determining the faulty rack in the logic cabinet 1 through the power cabinet 2 of the RGL system includes: when it is detected that the control rod group 4 in the mobile locked state under the power cabinet 2 is a shutdown rod group or a temperature rod group, determining that the faulty rack is a UPAT rack 11. Different control rod groups 4 are controlled by different racks in the logic cabinet 1. When it is determined that the control rod group 4 in the mobile locked state is a shutdown rod group or a temperature rod group, the faulty rack is the UPAT rack 11 for controlling the shutdown rod group and the temperature rod group. Figure 4 In the human-computer interaction interface shown, SA1, SA2, SB1, SB2, SC, SD1, SD2 are shutdown rod groups; R1, R2 are temperature rod groups. When the faulty rack is determined to be UPAT rack 11, Figure 4 The selection lever in the man-machine interface selects the UPAT rack 11, and then selects different temperature rod groups or shutdown rod groups in the man-machine interface to control them.

[0049] Optionally, in step S20, determining the faulty rack in the logic cabinet 1 through the power cabinet 2 of the RGL system includes: when detecting that the control rod group 4 in the mobile locking state under the power cabinet 2 is a power rod group, determining that the faulty rack is the UPP rack 12. Similarly, since different control rod groups 4 are controlled by different racks in the logic cabinet 1, when determining that the control rod group 4 in the mobile locking state is a power rod group, the faulty rack is the UPP rack 12 for controlling the power rod group. Figure 4 In the human-machine interaction interface shown, G1, G21, G21, N11, N12, N21, and N22 are all power rod groups. When the faulty rack is determined to be UPP rack 12, you can Figure 4 The selection lever in the human-machine interface selects the UPP rack 12, and then selects different power rod groups in the human-machine interface to control them.

[0050] S30, installing the control panel quick lifting and insertion device 3 to the RGL system, so that the control panel quick lifting and insertion device 3 is connected to the power cabinet 2 in communication, and then the control panel quick lifting and insertion device 3 controls the power cabinet 2 to release the movement locking state of the control rod group 4; after the movement locking state of the control rod group 4 is released, the control rod group 4 can be moved. It can be understood that after the control panel quick lifting and insertion device 3 is connected to the power cabinet 2 in communication, different parameter variables can be set for different control rod groups 4 according to the non-required rod position where the control rod group 4 is currently located, and the parameter variable represents the difference between the current non-required rod position and the required rod position to be corrected (the parameter variable can be equal to the number of deviation steps between the control rod group 4 and the required rod position), and then when executing the lifting and insertion event, each lifting and insertion action can be executed according to the parameter variable.

[0051] Optionally, the control panel quick lifting and insertion device 3 includes a user terminal 31, a data acquisition device 32 connected between the user terminal 31 and the power 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 to display a human-computer interaction interface for the nuclear power plant operator to enter control instructions; the data acquisition device 32 is used to send the control instructions to the power cabinet 2; the level conversion device 33 is used to convert the level of the data acquisition device 32 into the logic level of the RGL system. That is, the user terminal 31 can be a computer terminal device such as a laptop, pad, mobile phone, desktop computer, etc. The user terminal 31 can run the human-computer interaction interface, and then trigger the control instructions containing lifting and insertion events, fault clearing instructions, parameter variable modification instructions, etc. in the human-computer interaction interface (displayed by the human-computer interaction program). The data acquisition device 32 (NI) can realize communication with the human-computer interaction program, and then finally send the above-mentioned generated instructions to the power cabinet 2; the level conversion device 33 is used to realize the conversion of the logic level between the data acquisition device 32 and the RGL system.

[0052] Furthermore, the control panel quick insertion and extraction device 3 also includes a bus interface card 34 connected to the level conversion device 33, and the bus interface card 34 can realize the quick connection between the control panel quick insertion and extraction device 3 and the RGL system. The faulty rack includes a control card connected to the CPU board of the faulty rack; when the faulty rack of the logic cabinet 1 fails, the control card is withdrawn from the faulty rack, and the control panel quick insertion and extraction device 3 is plugged into the faulty rack through the bus interface card 34, so that the control panel quick insertion and extraction device 3 is connected to the power cabinet 2 corresponding to the faulty rack through the faulty rack, and then the power cabinet 2 connected to the control panel quick insertion and extraction device 3 is instructed to control the control rod group 4 corresponding to the faulty rack through the control command entered from the human-computer interaction interface.

[0053] The control panel quick insertion and extraction device 3 can be used as an additional offline device in the RGL system. It is not connected when the RGL system is operating normally. It is quickly inserted and used only when there is a faulty rack in the logic cabinet 1 of the RGL system, which improves the convenience of use. The control panel quick insertion and extraction device 3 can replace the faulty rack of the original logic cabinet 1 and communicate with the power cabinet 2. A human-computer interaction program with a human-computer interaction interface is set. The display content and logic of each part of the human-computer interaction interface are clear, which can facilitate operation and control, and can also take into account anti-ergonomics to avoid human operation errors.

[0054] Understandably, if Figure 4As shown, the correction 1 and correction 2 modes can be selected in the above human-machine interaction interface, and then in one of the above modes, the control panel quick lifting and insertion device 3 can communicate with the power supply cabinet 2 to control the control rod group 4. Among them, in the correction 1 mode: any rod group (shutdown rod group, temperature rod group or power rod group) can be selected to control the out-of-step correction of the selected rod group or / and meet certain experimental requirements. In the correction 1 mode, it is first necessary to control the rod position counter corresponding to the selected rod group not to change. The number of lifting and insertion steps of each rod group is determined by a dedicated rod position counter (such as Figure 4 As shown in the figure, the rod position counter is the 015QM or 016QM of the RGL system shown in the figure, where 015QM corresponds to the shutdown temperature rod group and 016QM corresponds to the power rod group). Secondly, when lifting and inserting the rods, the two sub-rod groups of the same rod group move at the same time; thirdly, in the correction 1 mode, the temperature rod group and the power rod group can be freely lifted and inserted between 5 steps and 225 steps, but the power rod does not follow the iterative procedure, that is, each rod group of the power rod group can operate independently.

[0055] In the correction 2 mode, any rod group (shutdown rod group, temperature rod group or power rod group) can be selected to correct the loss of step of the control rod group 4 or / and meet the requirements of certain experiments. In the correction 2 mode, first, the rod position counter of the control rod group 4 will change with the actual number of lifting and inserting steps, that is, the dedicated rod position counter corresponding to the selected rod group starts counting; secondly, when lifting and inserting rods, the two sub-rod groups of the same rod group move half a step apart; thirdly, in the correction 2 mode, the power rod group follows the iterative procedure, that is, the number of lifting and inserting steps of each rod group of the power rod group is linked.

[0056] It is understandable that under normal circumstances, the positions of two subgroups of the same rod group are the same, that is, the number of steps is the same. Due to the fault, the control rod group 4 corresponding to the faulty rack may be out of step during the movement; that is, the movement steps of different rod bundles of the same rod group are inconsistent. For example, there may be a situation where subgroup 1 is at 220 steps and subgroup 2 is at 119 steps. At this time, it is necessary to correct the rod position deviations (deviation refers to the deviation in the number of movement steps) of different subgroups through the above two correction modes, so that the two subgroups are at the same rod position.

[0057] Optionally, the control board quick insertion and extraction device 3 also includes a bus interface card 34 connected to the level conversion device 33; the faulty rack includes a control card connected to the CPU board of the faulty rack; the control board quick insertion and extraction device 3 can be used as an additional offline device in the RGL system, which is not connected when the RGL system is operating normally, and is only quickly intervened and used through the bus interface card 34 when there is a faulty rack in the logic cabinet 1 of the RGL system, thereby improving the convenience of use. The control board quick insertion and extraction device 3 is very small and can be quickly connected to the RGL system, taking over some of the functions implemented by the faulty rack of the logic cabinet 1 during the failure of the logic cabinet 1.

[0058] Furthermore, in the step S30, installing the control panel quick insertion and extraction device 3 into the RGL system includes:

[0059] The control card is controlled to withdraw from the faulty rack, and the control panel quick lifting and insertion device 3 is plugged into the faulty rack through the bus interface card 34, so that the control panel quick lifting and insertion device 3 is communicated with the power cabinet 2 corresponding to the faulty rack through the faulty rack, and then the power cabinet 2 connected to the control panel quick lifting and insertion device 3 is instructed to control the control rod group 4 corresponding to the faulty rack through the control instructions entered from the human-computer interaction interface.

[0060] That is, the above-mentioned bus interface card 34 is a bus access tool dedicated to the control board quick lifting and insertion device 3, which makes the access and use of the control board quick lifting and insertion device 3 more convenient and quick; the appearance and structure of the bus interface card 34 are consistent with the above-mentioned control card (the control card is communicated with the CPU board of the faulty rack), so when it is needed, the bus interface card 34 is inserted into the position where the control card was originally inserted in the faulty rack. Therefore, when using the bus interface card 34, the control card needs to be unplugged first; after the bus interface card 34 is inserted into the position where the control card was originally inserted in the faulty rack, it means that the control board quick lifting and insertion device 3 has been connected to the communication bus of the RGL system, and then the communication connection with the power cabinet 2 can be achieved through the communication bus.

[0061] Optionally, in step S30, the control panel quick lifting and insertion device 3 is communicated with the power cabinet 2, including: when the nuclear power plant operator triggers the run button in the human-computer interaction interface, the data acquisition device 32 and the level conversion device 33 are controlled to run, and the communication connection between the control panel quick lifting and insertion device 3 and the power cabinet 2 is established. That is, in this step, only the "click to run" button (that is, the run button) is clicked on the human-computer interaction interface to control the data acquisition device 32 and the level conversion device 33 to run, and the communication connection between the control panel quick lifting and insertion device 3 and the power cabinet 2 is established.

[0062] Optionally, in the step S30, after the control panel quick lifting and insertion device 3 is connected to the power cabinet 2 for communication, the step further includes: when the nuclear power plant operator triggers the stop button in the human-machine interaction interface, the data acquisition device 32 and the level conversion device 33 are controlled to stop running, and the communication connection between the control panel quick lifting and insertion device 3 and the power cabinet 2 is disconnected. That is, in this step, it is only necessary to click the "click to run" button (i.e., the run button) on the human-machine interaction interface, and the "click to run" button will be transformed into the "stop" button. At this time, by clicking the "stop" button, the data acquisition device 32 and the level conversion device 33 can be controlled to stop running, and the communication connection between the control panel quick lifting and insertion device 3 and the power cabinet 2 can be disconnected.

[0063] Optionally, in the step S30, controlling the power supply cabinet 2 to release the movement locking state of the control rod group 4 through the control panel quick lifting and inserting device 3 includes:

[0064] Sending a fault clearing instruction to the power cabinet 2 through the control panel quick lifting and inserting device 3, wherein the fault clearing instruction is generated after the nuclear power plant operator triggers the fault clearing button in the human-computer interaction interface;

[0065] The power supply cabinet 2 is instructed to execute the fault clearing event included in the fault clearing instruction to release the movement locking state of the control rod group 4.

[0066] That is, in this embodiment, it is only necessary to click the "dismiss" button (i.e., the fault clearing button) on the human-computer interaction interface to send a fault clearing instruction to the power cabinet 2, and then make the power cabinet 2 execute the fault clearing event contained in the fault clearing instruction to release the movement locking state of the control rod group 4. After that, the control panel quick lifting and insertion device 3 can send a control instruction to the power cabinet 2 to make the power cabinet 2 execute the lifting and insertion event contained in the control instruction, thereby controlling the control rod group 4 corresponding to the faulty rack to move to the required rod position. Before the control panel quick lifting and insertion device 3 sends the fault clearing instruction to the power cabinet 2, the control rod group 4 corresponding to the faulty rack is always in the movement locking state and cannot move.

[0067] Optionally, after step S30, it further includes: when the power cabinet 2 does not receive the control instruction sent by the control panel quick insertion and extraction device 3 within the preset time length, the power cabinet 2 is caused to execute a timeout event to send a timeout fault alarm to the preset fault handling party. In this embodiment, if the user does not operate in the human-computer interaction interface for a long time, the human-computer interaction software will periodically (the time interval does not exceed the preset time length) send a control instruction containing waiting information to the power cabinet 2. In this embodiment, if the power cabinet 2 does not receive any control instruction for more than a preset time length (for example, 6 seconds), it will execute a timeout event to send a timeout fault alarm to the preset fault handling party, and then the preset fault handling party will perform alarm processing according to the timeout fault alarm.

[0068] S40, sending a control instruction to the power cabinet 2 through the control panel quick lifting and insertion device 3, so that the power cabinet 2 executes the lifting and insertion event contained in the control instruction, thereby controlling the control rod group 4 corresponding to the faulty rack to move to the required rod position to eliminate the first group I0 of the generator set.

[0069] That is, when the rod position is required to be 225 steps, the step S40 can finally make the control rod group 4 corresponding to the faulty rack be lifted back by 225 steps to eliminate the first group I0 of the generator set, and avoid the generator set being retreated because the control rod group 4 is no longer in the required rod position for one hour. In addition, after step S40, the nuclear power plant operator needs to find the cause of the fault of the faulty rack as soon as possible and eliminate it. After eliminating the fault of the faulty rack, the bus interface card 34 of the control board quick lifting and plugging device 3 can be pulled out, and the control card can be reinserted to communicate and connect it with the CPU board of the faulty rack, and then the faulty rack that has been restored to normal (no longer has a fault) can be controlled through the power cabinet 2 to control the control rod group 4 corresponding to it.

[0070] Optionally, in step S40, instructing the power cabinet 2 to execute the lifting and inserting event contained in the control instruction includes:

[0071] Instruct the power supply cabinet 2 to obtain the parameter variable contained in the control instruction, where 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 faulty rack;

[0072] The power supply cabinet 2 is instructed to determine a moving rod timing according to the parameter variable, and then control the control rod group 4 corresponding to the faulty rack to execute the lifting and inserting event according to the moving rod timing.

[0073] Understandably, the moving rod sequence is composed of different numbers of lifting events and inserting events arranged in a preset sequence, and the moving rod sequence is set by the power supply cabinet 2 according to the parameter variables contained in the control instruction. The human-machine interaction interface can determine whether the next lifting and inserting event is a lifting event or an inserting event according to the moving rod sequence, and then, the nuclear power plant operator can click the "lifting step" button (corresponding to the lifting step event) or the "inserting step" button (corresponding to the inserting step event) on the human-machine interaction interface after checking the displayed content, and then, the power supply cabinet 2 controls the control rod group 4 to execute the lifting and inserting event corresponding to the pressed button.

[0074] Specifically, when the lifting and inserting event is a lifting event (the lifting event is triggered after the nuclear power plant operator triggers the lifting button in the human-machine interaction interface), the power supply cabinet 2 controls the control rod group 4 corresponding to the faulty rack to lift one step based on the current non-required rod position. When the lifting and inserting event is an inserting event (the inserting event is triggered after the nuclear power plant operator triggers the inserting button in the human-machine interaction interface), the power supply cabinet 2 controls the control rod group 4 corresponding to the faulty rack to insert one step based on the current non-required rod position.

[0075] Optionally, after instructing the power cabinet 2 to obtain the parameter variable included in the control instruction, the method further includes:

[0076] The parameter variable modification instruction including the variable value to be modified is sent to the power cabinet 2 through the control panel quick insertion and lifting device 3, and the variable value to be modified is recorded as a new parameter variable corresponding to the insertion and lifting event; wherein the parameter variable modification instruction is generated after the nuclear power plant operator enters the variable value to be modified in the human-computer interaction interface and triggers the parameter sending button;

[0077] The power supply cabinet 2 is instructed to determine a new moving rod timing according to the new parameter variable, and then control the control rod group 4 corresponding to the faulty rack to execute the lifting and inserting event according to the new moving rod timing.

[0078] That is, the parameter variables corresponding to the above-mentioned lifting and inserting events can be modified by the nuclear power plant operator on the human-machine interaction interface according to the needs, and only need to enter the variable value to be modified in the human-machine interaction interface and click the parameter sending button to send the parameter variable modification instruction containing the variable value to be modified to the power supply cabinet 2. And during the execution of the lifting and inserting event corresponding to a control instruction, since the rod position of the control rod group 4 changes in real time, at this time, the parameter variable will also be updated in real time.

[0079] The control method of the control rod group 4 of the RGL system of a nuclear power plant provided by the present invention, during the RGL test process, if it is monitored that a fault occurs in the logic cabinet 1 and the control rod group 4 is in a non-required rod position, in order to avoid the generator set being withdrawn due to untimely fault handling (after the RGL system fault causes the control rod group 4 to be out of the required rod position for one hour, the generator set will be withdrawn), the control panel quick lifting and insertion device 3 is used. Rapid intervention communicates with the power cabinet 2 and releases the movement locking state of the control rod group 4, and then sends a control instruction to the power cabinet 2 through the control panel quick lifting and insertion device 3, so that the power cabinet 2 executes the lifting and insertion event contained in the control instruction, thereby controlling the control rod group 4 corresponding to the faulty rack to move to the required rod position, so as to eliminate the first group I0 of the generator set, so that even if the control rod group 4 can be restored to the required rod position in time, the time for the control rod group 4 to be in the non-required rod position cannot last for one hour, thereby avoiding the restricted behavior of the generator set retreat; providing the on-site nuclear power plant operators with a larger fault handling time margin, greatly reducing the time pressure of the nuclear power plant operators, reducing the possibility of human errors due to time pressure, so that the nuclear power plant operators have sufficient time to eradicate the fault of the RGL system, and at the same time, the present invention avoids economic losses to the greatest extent, reduces unit losses and manpower consumption. At present, the control method of the control rod group 4 of the nuclear power plant RGL system has been successfully tested on the assembled RGL system minimum platform, realizing the function of moving the control rod group 4 to the required rod position when the logic cabinet 1 of the RGL system fails.

[0080] Optionally, in step S10, after determining whether the logic cabinet 1 of the RGL system fails, the following steps are performed:

[0081] When it is confirmed that the power cabinet 2 of the RGL system fails, the first LCS rack 21 in the power cabinet 2 that fails is determined, and after the first LCS rack 21 is replaced with a second LCS rack 21 of the same type in the RGL test environment, the logic cabinet 1 controls the control rod group 4 to move from the non-required rod position to the required rod position through the power cabinet 2; the second LCS rack 21 belongs to other power cabinets 2 of the same type as the failed power cabinet 2 in the RGL test environment. That is, in this embodiment, if the fault is caused by the power cabinet 2, at this time, the RGL test environment of the nuclear power plant usually has multiple completely identical power cabinets 2 (the RGL test environment of the nuclear power plant does not have multiple logic cabinets 1 of the same type, so the same method cannot be used to replace the faulty rack in the logic cabinet 1), so the other power cabinets 2 in the RGL test environment that are of the same type and are not currently needed (such as Figure 2 In the embodiment, only one LCS rack 21 is used in each of the two power cabinets 2. At this time, the other LCS racks 21 that are not currently in use in the power cabinet 2 can be used as the second LCS rack 21 to replace the failed first LCS rack 21), thereby quickly handling the fault and allowing the power cabinet 2 to quickly return to normal working status.

[0082] The embodiments described above are only used to illustrate the technical solutions of the present invention, rather than to limit the same. Although the present invention has been described in detail with reference to the aforementioned embodiments, those skilled in the art should understand that the technical solutions described in the aforementioned embodiments may still be modified, or some of the technical features may be replaced by equivalents. Such modifications or replacements do not deviate the essence of the corresponding technical solutions from the spirit and scope of the technical solutions of the embodiments of the present invention, and should all be included in the protection scope of the present invention.

Claims

1. A control rod group control method for a nuclear power plant RGL system, It is characterized in that include: During the RGL test, if it is monitored that the control rod group of the generator set is in a moving locked state corresponding to a non-required rod position, the generator set is recorded as the first group I0, and it is determined whether the logic cabinet of the RGL system is faulty; When it is confirmed that a logic cabinet of the RGL system fails, a faulty rack in the logic cabinet is determined through a power cabinet of the RGL system; the logic cabinet is communicatively connected with the power cabinet; the power cabinet is electrically connected with all control rod groups in the RGL system; the faulty rack is a UPAT rack or / and a UPP rack contained in the logic cabinet; The control panel quick lifting and insertion device is installed in the RGL system so that the control panel quick lifting and insertion device is connected to the power cabinet for communication, and then the power cabinet is controlled by the control panel quick lifting and insertion device to release the mobile locking state of the control rod group; the control panel quick lifting and insertion device includes 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 to display a human-computer interaction interface for nuclear power plant operators to enter control instructions; the data acquisition device is used to send the control instructions to the power cabinet; the level conversion device is used to convert the level of the data acquisition device into the logic level of the RGL system; the control panel quick lifting and insertion device also includes a bus interface card connected to the level conversion device, and the bus interface card can realize the quick docking of the control panel quick lifting and insertion device and the RGL system; A control instruction is sent to the power cabinet through the control panel quick lifting and insertion device, so that the power cabinet executes the lifting and insertion event contained in the control instruction, thereby controlling the control rod group corresponding to the faulty rack to move to the required rod position to eliminate the first group I0 of the generator set.

2. The control rod group control method of the RGL system of a nuclear power plant according to claim 1, It is characterized in that The determining the faulty rack in the logic cabinet through the power cabinet of the RGL system includes: When it is detected that the control rod group under the power cabinet that is in the moving locked state is a shutdown rod group or a temperature rod group, it is determined that the faulty rack is a UPAT rack.

3. The control rod group control method of the RGL system of a nuclear power plant according to claim 1, It is characterized in that The determining the faulty rack in the logic cabinet through the power cabinet of the RGL system includes: When it is detected that the control rod group in the movable locked state under the power cabinet is a power rod group, it is determined that the faulty rack is a UPP rack.

4. The control rod group control method of the RGL system of a nuclear power plant according to claim 1, It is characterized in that The control panel quick insertion and extraction device includes 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 to display a human-computer interaction interface for nuclear power plant operators to enter control instructions; the data acquisition device is used to send the control instructions to the power cabinet; The level conversion device is used to convert the level of the data acquisition device into the logic level of the RGL system.

5. The control rod group control method of the RGL system of a nuclear power plant according to claim 4, It is characterized in that The control board quick insertion and extraction device also includes a bus interface card connected to the level conversion device; the faulty rack includes a control card connected to the CPU board of the faulty rack; The method of installing the control panel quick insertion and extraction device into the RGL system includes: The control card is controlled to withdraw from the faulty rack, and the control panel quick lifting and insertion device is plugged into the faulty rack through the bus interface card, so that the control panel quick lifting and insertion device is communicated with the power cabinet corresponding to the faulty rack through the faulty rack, and then the power cabinet connected to the control panel quick lifting and insertion device is instructed to control the control rod group corresponding to the faulty rack through the control instructions entered from the human-computer interaction interface.

6. The control rod group control method of the RGL system of a nuclear power plant according to claim 4, It is characterized in that The step of causing the power cabinet to execute the lifting and inserting event contained in the control instruction includes: Instructing the power supply cabinet to obtain a parameter variable included in the control instruction, wherein the parameter variable is determined according to a current non-required rod position and the required rod position of a control rod group corresponding to the faulty rack; The power supply cabinet is instructed to determine a moving rod timing according to the parameter variable, and then control a control rod group corresponding to the faulty rack to execute the lifting and inserting event according to the moving rod timing.

7. The control rod group control method of the RGL system of a nuclear power plant according to claim 4, It is characterized in that After the power supply cabinet is instructed to obtain the parameter variables contained in the control instruction, the method further includes: Sending a parameter variable modification instruction containing the variable value to be modified to the power cabinet through the control panel quick insertion and lifting device, and recording the variable value to be modified as a new parameter variable corresponding to the insertion and lifting event; wherein the parameter variable modification instruction is generated after the nuclear power plant operator enters the variable value to be modified in the human-computer interaction interface and triggers the parameter sending button; The power supply cabinet is instructed to determine a new moving rod timing according to the new parameter variable, and then control the control rod group corresponding to the faulty rack to execute the lifting and inserting event according to the new moving rod timing.

8. The control rod group control method of the RGL system of a nuclear power plant according to claim 4, It is characterized in that After the control panel quick insertion and lifting device is installed in the RGL system so that the control panel quick insertion and lifting device is connected to the power cabinet for communication, and then the control panel quick insertion and lifting device is used to control the power cabinet to release the movement locking state of the control rod group, the method further includes: When the power cabinet does not receive the control instruction sent by the control panel quick lifting and plugging device within a preset time period, the power cabinet is made to execute a timeout event to send a timeout fault alarm to a preset fault processing party.

9. The control rod group control method of the RGL system of a nuclear power plant according to claim 4, It is characterized in that The method of controlling the power supply cabinet to release the movement locking state of the control rod group through the control panel quick lifting and inserting device includes: Sending a fault clearing instruction to the power cabinet through the control panel quick lifting and inserting device, wherein the fault clearing instruction is generated after the nuclear power plant operator triggers the fault clearing button in the human-computer interaction interface; The power supply cabinet is instructed to execute the fault clearing event contained in the fault clearing instruction to release the movement locking state of the control rod group.

10. The control rod group control method of the RGL system of a nuclear power plant according to claim 4, It is characterized in that The control panel quick insertion and extraction device is communicatively connected with the power supply cabinet, comprising: When the nuclear power plant operator triggers the run button in the human-machine interaction interface, the data acquisition device and the level conversion device are controlled to run, and a communication connection is established between the control panel quick lifting and plugging device and the power cabinet.

11. The control rod group control method of the RGL system of a nuclear power plant according to claim 10, It is characterized in that After the control panel quick insertion and extraction device is connected to the power cabinet for communication, the method further includes: When the nuclear power plant operator triggers the stop button in the human-machine interaction interface, the data acquisition device and the level conversion device are controlled to stop running, and the communication connection between the control panel quick lifting and plugging device and the power cabinet is disconnected.

12. The control rod group control method of the RGL system of a nuclear power plant according to claim 1, It is characterized in that After determining whether the logic cabinet of the RGL system fails, the method includes: When it is confirmed that the power cabinet of the RGL system fails, the first LCS rack in the power cabinet where the failure occurs is determined, and after the first LCS rack is replaced with a second LCS rack of the same type in the RGL test environment, the logic cabinet controls the control rod group to move from the non-required rod position to the required rod position through the power cabinet; the second LCS rack belongs to other power cabinets of the same type as the failed power cabinet in the RGL test environment.

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