A method for arranging a nuclear power plant control rod assembly in a core and a control method

Abstract

This application provides a method for arranging control rod assemblies in a nuclear power plant core. The method includes: Step 1, classifying control rod assemblies into three types based on their function: shutdown rod groups, non-primary regulating rod groups, and primary regulating rod groups; Step 2, establishing a control rod assembly replacement plan for each of the shutdown rod groups, primary regulating rod groups, and non-primary regulating rod groups; Step 3, during each refueling overhaul, replacing the control rod assemblies in the shutdown rod groups, non-primary regulating rod groups, and primary regulating rod groups according to the replacement plan. This application addresses the technical problem of extending the overall service life of control rod assemblies by adjusting the arrangement of control rod assemblies with different functions in the core.

Description

Technical Field

[0001] This application belongs to the field of nuclear power plant reactor operation and safety technology, specifically relating to a method for arranging and controlling the core of a nuclear power plant control rod assembly. Background Technology

[0002] Nuclear power plant reactor control rod assemblies play a crucial role in compensating for and regulating core reactivity, as well as in emergency rod removal for reactor shutdown. With increasing operating time, after reaching a certain service life, control rod assemblies may exhibit defects such as swelling, wear, and cracks, affecting their structural integrity. Simultaneously, as absorbent material is consumed, reactivity control capabilities also decline. Therefore, control rod assemblies must be replaced after reaching their designed service life. Currently, nuclear power plants only have regulations regarding the overall service life of control rod assemblies; extending this overall service life has become a pressing technical problem to be solved. Summary of the Invention

[0003] In view of this, this application provides a method for arranging control rod assemblies in the reactor core of a nuclear power plant. By adjusting the arrangement of control rod assemblies with different functions in the reactor core, the technical problem of how to extend the overall service life of the control rod assemblies can be solved.

[0004] The first aspect of this application provides a method for arranging control rod assemblies in the core of a nuclear power plant, the method comprising: Step 1: Based on the function of the reactor control rod assembly, the control rod assemblies are divided into three types: shutdown rod group, non-main control rod group, and main control rod group. The shutdown rod group is a control rod assembly that is not inserted into the reactor core during operation and is used for emergency rod dropping to shut down the reactor. The non-main control rod group is a control rod assembly that is occasionally inserted into the reactor core during operation, and is only inserted into the reactor core when shutting down to reduce power and eliminate axial xenon oscillation. The main control rod group is a control rod assembly that is inserted into the reactor core for a long time during normal operation and is used for daily reactivity control.

[0005] Step 2: For the shutdown rod group, the main regulating rod group, and the non-main regulating rod group, set a control rod assembly replacement plan. The control rod assembly replacement plan includes that the use time of the control rod assembly in the main regulating rod group shall not exceed the first preset number of fuel cycles; the use time of the control rod assembly in the non-main regulating rod group shall not exceed the second preset number of fuel cycles; and the control rod assembly in the shutdown rod group shall not be in the same position in the core for a third consecutive preset number of fuel cycles.

[0006] Step 3: During each refueling overhaul, the control rod assemblies in the stopped stack rod group, non-main regulating rod group, and main regulating rod group shall be replaced according to the control rod assembly replacement plan.

[0007] In one specific embodiment of this application, the first preset number of fuel cycles is 1 fuel cycle.

[0008] In one specific embodiment of this application, the second preset number of fuel cycles is 2 fuel cycles.

[0009] In one specific embodiment of this application, the third preset number of fuel cycles is two fuel cycles.

[0010] A second aspect of this application provides a core control method for a nuclear power plant control rod assembly, the method comprising: Step 10: Obtain the control rod assembly replacement plan. The control rod assembly replacement plan includes: the control rod assembly in the main control rod group shall not be used for more than a first preset number of fuel cycles; the control rod assembly in the non-main control rod group shall not be used for more than a second preset number of fuel cycles; and the control rod assembly in the shutdown rod group shall not be in the same position in the core for a third preset number of consecutive fuel cycles. Step 20: During each refueling overhaul, according to the control rod assembly replacement plan and user control instructions, the control rod assemblies in the stopped stack rod group, non-main regulating rod group, and main regulating rod group are replaced according to the control rod assembly replacement plan.

[0011] A third aspect of this application provides a computer apparatus including a processor and a memory. The processor is used to execute a nuclear power plant control rod assembly core control method according to a second aspect of this application. The memory is used to store executable instructions for the processor.

[0012] The fourth aspect of this application provides a computer-readable storage medium storing executable instructions for a computer. When executed by a processor, the executable instructions implement a core control method for a nuclear power plant control rod assembly according to the second aspect of this application.

[0013] The fifth aspect of this application provides a computer program product, including a computer program / instructions, which, when executed by a processor, implements a nuclear power plant control rod assembly core control method according to the second aspect of this application.

[0014] The beneficial effects of the technical solution of this application are as follows: by adjusting the arrangement of different functional control rod assemblies in the reactor core, the utilization efficiency of the control rod assemblies can be improved, the service life of the control rod assemblies can be extended, and the replacement frequency of the control rod assemblies can be reduced. While reducing the replacement frequency and procurement cost of the control rod assemblies, the amount of high-level radioactive waste generated can be reduced, which has significant economic and social benefits. Attached Figure Description

[0015] Figure 1 The diagram shown is a schematic flow chart of a nuclear power plant control rod assembly core arrangement method according to an embodiment of this application.

[0016] Figure 2The diagram shown is a layout of a control rod assembly for a nuclear power plant according to an embodiment of this application.

[0017] Figure 3 The diagram shown is a schematic diagram of the arrangement of a control rod assembly in a nuclear power plant before adjustment, according to an embodiment of this application.

[0018] Figure 4 As shown Figure 3 The illustrated embodiment provides a schematic diagram of the adjusted arrangement of a control rod assembly in a nuclear power plant. Detailed Implementation

[0019] The technical solutions of the embodiments of this application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of this application, and not all embodiments. Based on the embodiments of this application, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of this application.

[0020] This application provides at least one embodiment of a method for arranging control rod assemblies in a nuclear power plant core, referencing... Figure 1 The core arrangement method for the control rod assembly of this nuclear power plant includes the following steps.

[0021] Step 1: Based on the function of the reactor control rod assembly, control rod assemblies are classified into three types: shutdown rod groups, non-primary control rod groups, and primary control rod groups. Shutdown rod groups are control rod assemblies that are not inserted into the core during operation and are used for emergency shutdown. Non-primary control rod groups are control rod assemblies that are occasionally inserted into the core during operation, only for power reduction during shutdown and elimination of axial xenon oscillation. Primary control rod groups are control rod assemblies that are permanently inserted into the core during normal operation and are used for routine reactivity control.

[0022] Careful study revealed that the cumulative neutron flux received by the control rod assembly in the reactor core is primarily generated during core insertion, and is relatively low when the core is at its upper limit. During routine operation, only the main control rod group is inserted into the core for extended periods and requires frequent movement for routine core reactivity control, while the non-main control rod groups are inserted only occasionally. Therefore, limiting the operating time of the control rod assembly between the main and non-main control rod groups can significantly reduce absorber material consumption and irradiation damage to structural materials, while also reducing wear caused by control rod assembly movement.

[0023] Because of the high reactor core flow rate, if the control rod assembly is located in the same core position of the shutdown rod group for multiple cycles, hydraulic impact disturbances may cause long-term wear at a certain location on the control rod assembly. Therefore, by adjusting the arrangement of the control rod assembly in the shutdown rod group each cycle, the severe wear caused by the control rod assembly being in the same position on the upper part of the core for a long time can be avoided, thus preventing premature replacement of the control rod assembly.

[0024] Step 2: Set control rod assembly replacement plans for the shutdown rod group, main regulating rod group, and non-main regulating rod group. The control rod assembly replacement plan includes: the control rod assembly usage time in the main regulating rod group shall not exceed a first preset number of fuel cycles; the control rod assembly usage time in the non-main regulating rod group shall not exceed a second preset number of fuel cycles; and the control rod assembly in the shutdown rod group shall not be in the same position in the core for a third consecutive preset number of fuel cycles.

[0025] Step 3: During each refueling overhaul, the control rod assemblies in the stopped stack rod group, non-main regulating rod group, and main regulating rod group shall be replaced according to the control rod assembly replacement plan.

[0026] According to the technical solution provided in this application, by classifying control rod assemblies into three types based on their functions—shutdown rod groups, non-main regulating rod groups, and main regulating rod groups—and setting corresponding replacement plans for each type of control rod assembly, these three types of control rod assemblies are replaced according to the replacement plans during refueling overhauls. This improves the utilization efficiency of the control rod assemblies, rationally allocates the time and number of actions of the control rod assemblies under irradiation in the reactor core, reduces the consumption of absorber materials and the irradiation damage to structural materials, and avoids severe wear of the control rod assemblies caused by them being in the same position on the upper part of the reactor core for a long time. Furthermore, by adjusting the arrangement of control rod assemblies with different functions in the reactor core, the service life of the control rod assemblies is extended, and the replacement frequency is reduced, resulting in significant economic benefits. It also reduces the amount of high-level radioactive waste generated by frequent control rod assembly replacements, resulting in significant social benefits. Finally, it reduces the occupation of radioactive waste in the spent fuel pool, creating conditions for subsequent dry storage and offloading of spent fuel.

[0027] In at least one embodiment of this application, the first preset number of fuel cycles is 1 fuel cycle.

[0028] In at least one embodiment of this application, the second preset number of fuel cycles is 2 fuel cycles.

[0029] In at least one embodiment of this application, the third preset number of fuel cycles is two fuel cycles.

[0030] Specifically, the control rod assembly replacement plan includes: The control rod assembly in the main regulating rod group is used for no more than one fuel cycle. The control rod assembly in the non-main regulating rod group shall be used for no more than two fuel cycles. The control rod assembly in the shutdown rod group must not be in the same position in the reactor core for two consecutive fuel cycles.

[0031] The following describes the method provided in this application in detail, taking the selection of a core arrangement replacement scheme for a certain cycle control rod assembly as the description object. The specific implementation method is as follows.

[0032] Figure 2 The top number indicates the core location, the middle number indicates the control rod assembly group number, and a blank space indicates that no control rod assembly is installed at that location. For example, the top left corner shows that the core location is 133 and the control rod assembly group number is 10. Figure 3 and Figure 4 The bottom number is the control rod assembly number (such as N001, N002, N003, N004, N005).

[0033] The reactor core in this example has 103 control rod assemblies, each with identical structure and materials. Based on their location and function, the 103 control rod assemblies are divided into groups 1-10. Groups 1-7 are shutdown rod groups, not inserted into the core during operation, serving as emergency rod-drop shutdown units; groups 8-9 are non-primary control rod groups, occasionally inserted into the core during operation to reduce power and eliminate axial xenon oscillations; group 10 is the primary control rod group, inserted into the core during operation for routine reactivity control.

[0034] When developing a control rod replacement plan for each major overhaul, the following requirements must be followed: The control rod assembly in the 10th main regulating rod group is used for no more than one fuel cycle. In the 8th and 9th groups of non-main regulating rods, the control rod assembly is used for no more than 2 fuel cycles. In the shutdown rod group, the control rod assembly must not be in the same position in the core for two consecutive cycles.

[0035] Assume that in a nuclear power plant, the control rod assembly of the 10th group of the main regulating rod group, located at core position 31, is numbered N001; the control rod assembly of the 8th group of the non-main regulating rod group, located at core position 11, is numbered N002; the control rod assembly of the 2nd group of the shutdown rod group, located at core position 9, is numbered N003; the control rod assembly of the 4th group of the shutdown rod group, located at core position 10, is numbered N004; and the control rod assembly of the 5th group of the shutdown rod group, located at core position 12, is numbered N005. Figure 3 As shown.

[0036] After the previous fuel cycle, according to the requirement that the control rod assembly in the 10th main regulating rod group should not be used for more than one fuel cycle, the control rod assembly numbered N001 will no longer be placed in the main regulating rod group during its lifespan. Other control rod assemblies that have not been in the main regulating rod group can be selected (such as N003). That is, the control rod assembly at core position 31 in the next cycle will be numbered N003, and the control rod assembly at core position 9 will be numbered N001. According to the requirement that the control rod assembly in the 8th-9th non-main regulating rod groups should not be used for more than two fuel cycles, if the control rod assembly numbered N002 has not been used for more than two fuel cycles in the non-main regulating rod groups, it can continue to be placed in the non-main regulating rod groups. That is, the control rod assembly at core position 11 in the next cycle will be numbered N002. According to the requirement that control rod assemblies in the shutdown rod group should not be in the same position for two consecutive fuel cycles, the control rod assembly at core position 10 in the next cycle will be numbered N005, and the control rod assembly at core position 12 will be numbered N004. Figure 4 As shown.

[0037] At least one embodiment of this application provides a core control method for a nuclear power plant control rod assembly, wherein the execution entity of the nuclear power plant control rod assembly core control method can be a processor of a computer device. The nuclear power plant control rod assembly core control method includes the following steps.

[0038] Step 10: Obtain the control rod assembly replacement plan. The control rod assembly replacement plan includes: the control rod assembly in the main control rod group will not be used for more than a first preset number of fuel cycles; the control rod assembly in the non-main control rod group will not be used for more than a second preset number of fuel cycles; and the control rod assembly in the shutdown rod group will not be in the same position in the core for a third consecutive preset number of fuel cycles.

[0039] Step 20: During each refueling overhaul, according to the control rod assembly replacement plan and user control instructions, the control rod assemblies in the stopped stack rod group, non-main regulating rod group, and main regulating rod group are replaced according to the control rod assembly replacement plan.

[0040] In some embodiments, the computer device may display the usage time of each control rod assembly at the corresponding position and prompt for replacement according to the control rod assembly replacement plan. The user can set the replacement plan according to the prompt information, and after clicking "confirm" on the computer device, the user control command is given. The processor in the computer device can execute the set replacement plan according to the user control command.

[0041] In other embodiments, the computer device may display the usage time of each control rod assembly at the corresponding position and provide specific suggested replacement schemes according to the control rod assembly replacement plan. The user can provide a final replacement scheme based on the suggested replacement schemes, and after clicking "confirm" on the computer device, the user control command is given. The processor in the computer device can execute the final replacement scheme according to the user control command.

[0042] At least one embodiment of this application also provides a computer device including a processor and a memory. The processor is used to execute a nuclear power plant control rod assembly core control method provided in any of the above embodiments of this application. The memory is used to store executable instructions of the processor, such as application programs. The number of processors can be one or more. The application programs stored in the memory can include one or more modules, each corresponding to a set of instructions. Furthermore, the processor is configured to execute instructions to perform the above-described nuclear power plant control rod assembly core control method.

[0043] The computer device may also include a power supply component configured for power management, a wired or wireless network interface configured to connect the computer device to a network, and an input / output (I / O) interface. The computer device can operate on an operating system stored in memory, such as Windows Server. TM Mac OSX TM Unix TM Linux TM FreeBSD TM Or similar.

[0044] At least one embodiment of this application also provides a computer-readable storage medium storing executable instructions for a computer. When executed by a processor, the executable instructions implement a nuclear power plant control rod assembly core control method provided in any of the above embodiments of this application.

[0045] A non-transitory computer-readable storage medium, when the instructions in the storage medium are executed by the processor of the computer device, enables the computer device to perform the nuclear power plant control rod assembly core control method. The nuclear power plant control rod assembly core control method is executed by an agent program.

[0046] Those skilled in the art will recognize that the algorithmic steps of the various examples described in conjunction with the embodiments disclosed in this application can be implemented in electronic hardware, or a combination of computer software and electronic hardware. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementation should not be considered beyond the scope of this application.

[0047] At least one embodiment of this application also provides a computer program product, including a computer program / instruction, which, when executed by a processor, implements a nuclear power plant control rod assembly core control method provided in any of the above embodiments of this application.

[0048] If the aforementioned functions are implemented as software functional units and sold or used as independent products, they can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, or a part of the technical solution, can be embodied in the form of a computer program product. This computer program product is stored in a storage medium and includes several instructions to cause a computer device (which may be a personal computer, server, or network device, etc.) to execute all or part of the steps of the nuclear power plant control rod assembly core control method of the various embodiments of this application. The aforementioned storage medium includes various media capable of storing program checksums, such as USB flash drives, portable hard drives, read-only memory (ROM), random access memory (RAM), magnetic disks, or optical disks.

[0049] It should be noted that the combination of the technical features in the embodiments of this application is not limited to the combination methods described in the embodiments of this application or the combination methods described in specific embodiments. All technical features described in this application can be freely combined or combined in any way, unless they contradict each other.

[0050] As indicated in this application and claims, unless the context clearly indicates otherwise, the words "a," "an," and / or "the" do not specifically refer to the singular and may also include the plural. Generally speaking, the term "comprising" only indicates that it includes the explicitly identified steps and elements, which do not constitute an exclusive list, and the method or apparatus may also include other steps or elements.

[0051] The terms "first," "second," etc., are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Therefore, a feature defined with "first," "second," etc., may explicitly or implicitly include one or more of that feature.

[0052] The above description is merely a preferred embodiment of this application and is not intended to limit this application. Any modifications or equivalent substitutions made within the spirit and principles of this application should be included within the protection scope of this application.

Claims

1. A method of core arrangement for a nuclear power plant control rod assembly, characterized by, include: Step 1: Based on the function of the reactor control rod assembly, the control rod assemblies are divided into three types: shutdown rod group, non-main control rod group, and main control rod group. The shutdown rod group is a control rod assembly that is not inserted into the reactor core during operation and is used for emergency shutdown by dropping rods. The non-main control rod group is a control rod assembly that is occasionally inserted into the reactor core during operation, and is only inserted into the reactor core when shutting down to reduce power and eliminate axial xenon oscillation. The main control rod group is a control rod assembly that is inserted into the reactor core for a long time during normal operation and is used for daily reactivity control. Step 2: For the shutdown rod group, the main regulating rod group, and the non-main regulating rod group, set a control rod assembly replacement plan. The control rod assembly replacement plan includes that the use time of the control rod assembly in the main regulating rod group does not exceed the first preset number of fuel cycles; the use time of the control rod assembly in the non-main regulating rod group does not exceed the second preset number of fuel cycles; and the control rod assembly in the shutdown rod group must not be in the same position in the core for a third consecutive preset number of fuel cycles. Step 3: During each refueling overhaul, the control rod assemblies in the stopped stack rod group, non-main regulating rod group, and main regulating rod group shall be replaced according to the control rod assembly replacement plan.

2. The method for arranging control rod assemblies in a nuclear power plant core according to claim 1, characterized in that, The first preset number of fuel cycles is 1 fuel cycle.

3. The method for arranging control rod assemblies in a nuclear power plant core according to claim 1, characterized in that, The second preset number of fuel cycles is 2 fuel cycles.

4. The method for arranging control rod assemblies in a nuclear power plant core according to claim 1, characterized in that, The third preset number of fuel cycles is 2 fuel cycles.

5. A method for core control of a nuclear power plant control rod assembly, characterized in that, The control rod assembly is arranged using a core arrangement method for a nuclear power plant control rod assembly as described in any one of claims 1 to 4, wherein the core control method for the nuclear power plant control rod assembly includes: Step 10: Obtain the control rod assembly replacement plan. The control rod assembly replacement plan includes: the control rod assembly in the main control rod group shall not be used for more than a first preset number of fuel cycles; the control rod assembly in the non-main control rod group shall not be used for more than a second preset number of fuel cycles; and the control rod assembly in the shutdown rod group shall not be in the same position in the core for a third preset number of consecutive fuel cycles. Step 20: During each refueling overhaul, according to the control rod assembly replacement plan and user control instructions, the control rod assemblies in the stopped stack rod group, non-main regulating rod group, and main regulating rod group are replaced according to the control rod assembly replacement plan.

6. A computer device, characterized in that, include: A processor for executing the nuclear power plant control rod assembly core control method as described in claim 5; as well as Memory for storing the executable instructions of the processor.

7. A computer-readable storage medium having executable instructions stored thereon, characterized in that, When the executable instructions are executed by the processor, they implement the core control method for a nuclear power plant control rod assembly as described in claim 5.

8. A computer program product comprising a computer program / instructions, characterized in that, When the computer program / instructions are executed by the processor, they implement the core control method for a nuclear power plant control rod assembly as described in claim 5.

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