Nuclear power reactor core control rod sequence exchange method, device, equipment, medium and product
By determining the insertion position of the target control rod group in the nuclear power reactor core and exchanging them sequentially, the problem of significant burnup shadow effects in existing technologies has been solved, thereby improving the operating efficiency and safety of the nuclear power reactor core.
Patent Information
- Application Number
- CN202511433235.4
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-10-09
- Publication Date
- 2026-01-06
AI Technical Summary
Existing control rod sequential exchange strategies are ill-suited to the complex operating environment of nuclear power reactor cores, resulting in significant burnup shadow effects and reduced operating efficiency and safety of nuclear power reactor cores.
By determining the current and target insertion positions of the target control rod group, and performing sequential exchanges according to preset conditions, the control rod sequential exchange device and method of nuclear power reactor core are adopted to automatically control the insertion sequence exchange of control rods.
It effectively prevents the generation of excessive burn-up shadows in the fuel and improves the operating efficiency and safety of the nuclear power reactor core.
Smart Images

Figure CN121281879A_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of nuclear power control technology, and in particular to methods, apparatus, equipment, media and products for sequentially exchanging control rods in nuclear power reactor cores. Background Technology
[0002] The control rods in a nuclear power plant reactor core are one of the core components and the only moving parts within the reactor. Their insertion position directly affects the reactor core's startup, power operation, and normal shutdown. According to the mechanical compensation control strategy, the insertion order of the control rods must be changed periodically during the fuel cycle to ensure the burnup balance of the components containing the control rods and reduce the generation of burnup shadows.
[0003] However, based on the operating experience of nuclear power plants, the existing control rod sequence exchange strategy and parameter tuning methods have the following problems in the actual operation of nuclear power plants: (1) The nuclear power core is in different operating states at all times, and its operating power also has large transient changes. Adjusting the insertion order of the control rod group by setting fixed control rod sequence exchange parameters is difficult to adapt to the complex operating environment of the nuclear power core; (2) In order to better adapt to the operating conditions of the nuclear power core, the control rods need to manually adjust the sequence exchange control parameters multiple times by manual judgment when adjusting the insertion order, which greatly affects the operating efficiency and safety of the nuclear power core.
[0004] Therefore, how to change the insertion order of control rods in nuclear power reactor cores, ensure the burnup balance of fuel assemblies, reduce the impact of burnup shadow on nuclear power reactor cores, and ensure the operating efficiency and safety of nuclear power reactor cores are technical issues that urgently need to be studied by those skilled in the art. Summary of the Invention
[0005] This invention provides a method, apparatus, equipment, medium, and product for sequentially exchanging control rods in a nuclear power reactor core, in order to prevent excessive burn-out shadows in the fuel of the control rods, reduce the impact of burn-out shadows on the nuclear power reactor core, and improve the operating efficiency and safety of the nuclear power reactor core.
[0006] According to one aspect of the present invention, a method for sequentially exchanging control rods in a nuclear power reactor core is provided, comprising:
[0007] Based on the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core, determine the target control rod group that satisfies the current sequence exchange cycle;
[0008] If it is determined that the target control rod group meets the preset control rod sequence exchange conditions, then the current insertion position of the target control rod group is determined, and the target insertion position is determined based on the current insertion position;
[0009] Based on the current insertion position and the target insertion position of the target control rod group, determine the sequential exchange execution strategy of the target control rod group;
[0010] According to the sequential exchange execution strategy, the control rods in the target control rod group are controlled to exchange sequentially.
[0011] According to another aspect of the present invention, a control rod sequential exchange device for a nuclear power reactor core is provided, comprising:
[0012] The control rod group acquisition module is used to determine the target control rod group that satisfies the current sequence exchange cycle based on the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core.
[0013] The insertion position determination module is used to determine the current insertion position of the target control rod group if it is determined that the target control rod group meets the preset control rod sequence exchange conditions, and to determine the target insertion position based on the current insertion position;
[0014] The sequential exchange execution strategy determination module is used to determine the sequential exchange execution strategy of the target control rod group based on the current insertion position and the target insertion position of the target control rod group;
[0015] The sequential exchange execution module is used to control the sequential exchange of each control rod in the target control rod group according to the sequential exchange execution strategy.
[0016] According to another aspect of the present invention, an electronic device is provided, the electronic device comprising:
[0017] At least one processor; and
[0018] A memory communicatively connected to the at least one processor; wherein,
[0019] The memory stores a computer program that can be executed by the at least one processor, which enables the at least one processor to perform the control rod sequential exchange method for nuclear power reactor cores according to any embodiment of the present invention.
[0020] According to another aspect of the present invention, a computer-readable storage medium is provided, the computer-readable storage medium storing computer instructions for causing a processor to execute and implement the control rod sequential exchange method for a nuclear power reactor core according to any embodiment of the present invention.
[0021] According to another aspect of the present invention, a computer program product is provided, the computer program product comprising a computer program that, when executed by a processor, implements the control rod sequential exchange method for nuclear power reactor cores as described in any embodiment of the present invention.
[0022] The technical solution of this invention involves determining a target control rod group that satisfies the current sequential exchange cycle based on the current sequential exchange cycle corresponding to at least one control rod group in the target nuclear power reactor core; if the target control rod group satisfies the preset control rod sequential exchange conditions, then determining the current insertion position of the target control rod group and, based on the current insertion position, determining the target insertion position; determining the sequential exchange execution strategy of the target control rod group based on the current insertion position and the target insertion position; and controlling the sequential exchange of each control rod in the target control rod group according to the sequential exchange cycle corresponding to the control rod group in the nuclear power reactor core, and when the control rod group satisfies the preset control rod exchange execution conditions, sequentially exchanging each control rod in the control rod group based on the current insertion position and the target insertion position. This prevents excessive burnup shadows from appearing in the fuel containing the control rods, greatly reducing the impact of burnup shadows on the nuclear power reactor core and improving the operating efficiency and safety of the nuclear power reactor core.
[0023] It should be understood that the description in this section is not intended to identify key or essential features of the embodiments of the present invention, nor is it intended to limit the scope of the invention. Other features of the invention will become readily apparent from the following description. Attached Figure Description
[0024] To more clearly illustrate the technical solutions in the embodiments of the present invention, the accompanying drawings used in the description of the embodiments will be briefly introduced below. Obviously, the accompanying drawings described below are only some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.
[0025] Figure 1 This is a flowchart of a method for sequentially exchanging control rods in a nuclear power reactor core according to Embodiment 1 of the present invention;
[0026] Figure 2 This is a flowchart of a method for sequentially exchanging control rods in a nuclear power reactor core according to Embodiment 2 of the present invention;
[0027] Figure 3 This is a schematic diagram of the structure of a control rod sequential exchange device for a nuclear power reactor core according to Embodiment 3 of the present invention;
[0028] Figure 4 This is a schematic diagram of the structure of an electronic device for implementing the control rod sequential exchange method of a nuclear power reactor core according to an embodiment of the present invention. Detailed Implementation
[0029] To enable those skilled in the art to better understand the present invention, the technical solutions of the present invention will be clearly and completely described below with reference to the accompanying drawings of the embodiments of the present invention. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort should fall within the scope of protection of the present invention.
[0030] It should be noted that the terms "first," "second," etc., in the specification, claims, and accompanying drawings of this invention are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence. It should be understood that such data can be interchanged where appropriate so that the embodiments of the invention described herein can be implemented in orders other than those illustrated or described herein. Furthermore, the terms "comprising" and "having," and any variations thereof, are intended to cover a non-exclusive inclusion; for example, a process, method, system, product, or apparatus that comprises a series of steps or units is not necessarily limited to those steps or units explicitly listed, but may include other steps or units not explicitly listed or inherent to such processes, methods, products, or apparatus.
[0031] Example 1
[0032] Figure 1 This invention provides a flowchart of a method for sequentially exchanging control rods in a nuclear power reactor core, according to Embodiment 1. This embodiment is applicable to situations where the operating efficiency and safety of the nuclear power reactor core are significantly reduced during the sequential exchange of control rods. This method can be executed by a control rod sequential exchange device, which can be implemented in hardware and / or software and can be configured in an electronic device. Figure 1 As shown, the method includes:
[0033] S110. Determine the target control rod group that satisfies the current sequence exchange cycle based on the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core.
[0034] The current sequence exchange period can be calculated based on the current state of each control rod group, determining the time period for exchanging the insertion order of each control rod in the control rod group. Specifically, it can be calculated based on the operating power of the nuclear power reactor core. It should be noted that the current sequence exchange period for each control rod group can change in real time with the operating power of the nuclear power reactor core.
[0035] The target control rod group refers to the control rod group in the nuclear power reactor core whose operating time period in the current control rod insertion order has reached or is approaching the time period for exchanging the insertion order of the control rods. Specifically, it can be the control rod group whose insertion order needs to be exchanged based on the current order exchange period of each control rod group in the nuclear power reactor core and the operating time period of each control rod group in the current insertion order. For example, if the nuclear power reactor core may include control rod group A, control rod group B, and control rod group C, then the current order exchange period for control rod group A can be 90 days, the current order exchange period for control rod group B can be 50 days, and the current order exchange period for control rod group C can be 100 days. Furthermore, if the operating time cycle of control rod group A with the current insertion order of each control rod is 90 days, the operating time cycle of control rod group B with the current insertion order of each control rod is 70 days, and the operating time cycle of control rod group C with the current insertion order of each control rod is 45 days, then control rod group A can be determined as the target control rod group. This embodiment does not impose specific limitations on this.
[0036] S120. If it is determined that the target control rod group meets the preset control rod sequence exchange conditions, then determine the current insertion position of the target control rod group, and determine the target insertion position based on the current insertion position.
[0037] Specifically, the control rod sequence exchange conditions refer to the requirements that the control rod group and the nuclear power core must meet when exchanging the insertion order of each control rod in the control rod group. These requirements may include the insertion positions of each control rod in the control rod group and the required operating power of the nuclear power core. Specifically, the insertion position requirements for each control rod in the control rod group may include the insertion position requirements for the pilot control rod and the temperature control rod; the nuclear power core operating power requirements may include determining whether the operating power of the nuclear power core supports the sequential exchange of the control rods and whether the operating power of the nuclear power core is stable. In particular, the control rod sequence exchange conditions can be preset by technicians based on practical operational experience.
[0038] The current insertion position refers to the real-time insertion order of each control rod in the control rod group, while the target insertion position refers to the position order after exchanging the insertion order of each control rod in the control rod group. Specifically, the insertion position of the control rod group can be preset by a technician, and the insertion order of each control rod in the control rod group is fixed. For example, continuing the previous example, if the target control rod group A may include control rods A1, A2, A3, and A4, then the insertion order of each control rod in the target control rod group A may include position order 1: control rod A1-control rod A2-control rod A3-control rod A4, and position order 2: control rod A4-control rod A3-control rod A2-control rod A1. Furthermore, when it is determined that the target control rod group meets the preset control rod order exchange conditions, the real-time insertion order of each control rod in the target control rod group is determined. Based on the real-time insertion order of each control rod, the insertion order after sequentially swapping the control rods can be directly obtained. For example, if the real-time insertion order of each control rod in the target control rod group is position order 1: control rod A1-control rod A2-control rod A3-control rod A4, then the insertion order after sequentially swapping the control rods can be position order 2: control rod A4-control rod A3-control rod A2-control rod A1.
[0039] Optionally, before determining the current insertion position of the target control rod group and determining the target insertion position based on the current insertion position, the method further includes: obtaining distance information between each control rod in the target control rod group and the target nuclear power reactor core; determining whether the target control rod group is in the same axial position based on the distance information; if not, determining the pilot control rod in the target control rod group and determining the current insertion position of the target control rod group based on the pilot control rod.
[0040] Among them, the pilot control rod can be the first control rod to perform the sequential exchange operation when the control rods in the control rod group are sequentially exchanged. Specifically, it can be the control rod with the smallest distance from the nuclear reactor core among the control rods in the control rod group.
[0041] Specifically, determining whether the target control rod group is in the same axial position can involve determining whether the distance information between each control rod in the target control rod group and the target nuclear power core is the same. More specifically, if the distance information between each control rod in the target control rod group and the target nuclear power core is different, the control rod with the smallest distance to the nuclear power core is determined based on the distance information between each control rod and the nuclear power core, and this rod is used as the lead control rod for sequential exchange within the target control rod group. Then, based on the lead control rod, the current insertion position of the control rod group is determined. For example, continuing the previous example, if the distance information between control rod A1 and the nuclear power core in target control rod A can be 55 steps, the distance information between control rod A2 and the nuclear power core can be 70 steps, the distance information between control rod A3 and the nuclear power core can be 85 steps, and the distance information between control rod A4 and the nuclear power core can be 105 steps, then control rod A1 can be determined as the pilot control rod, and the current insertion position order of target control rod group A can be determined as control rod A1-control rod A2-control rod A3-control rod A4.
[0042] Furthermore, if it is determined that the target control rod group is in the same axial position, the insertion positions of each control rod in the target control rod group can be directly exchanged in sequence without determining the current insertion position of the target control rod group. This exchange method is applicable to a stopped nuclear power core in which all control rods have been inserted. Usually, the exchange is carried out before the nuclear power core is put into operation, or the insertion positions of each control rod are exchanged in sequence immediately when the target control rod group is in the same position (such as when it is completely withdrawn).
[0043] Optionally, the control rod sequence exchange condition includes a first sequence exchange condition; the method for determining whether the target control rod group meets the first sequence exchange condition is as follows: determine the pilot control rod and the insertion position information of the pilot control rod in the target control rod group; based on the insertion position information of the pilot control rod, determine whether it meets the preset pilot control rod insertion position information condition; if it meets the preset pilot rod insertion position information condition, then determine that the target control rod group meets the first sequence exchange condition.
[0044] The first sequential exchange condition can be determining whether the insertion position information of the pilot control rod in the target control rod group meets the preset pilot control rod insertion position information conditions. Specifically, after obtaining the pilot control rods in the target control rod group and their insertion position information, the insertion position information of the pilot control rods can be compared with the preset pilot control rod insertion position information conditions to obtain a position information comparison result; based on the position information comparison result, it can be determined whether the target control rod meets the first sequential exchange condition. More specifically, it can be determined by finding the distance information between the pilot control rod and the nuclear power core, and comparing the obtained distance information with the preset distance information conditions between the pilot control rod and the nuclear power core. For example, if the distance information between the pilot control rod and the nuclear power core is 60 steps, and the preset distance information conditions between the pilot control rod and the nuclear power core can be 50-150 steps, then it can be determined that the insertion position information of the pilot control rod meets the preset pilot control rod insertion position information conditions, that is, the target control rod group meets the first sequential exchange condition. This embodiment does not impose specific limitations on this.
[0045] Furthermore, if the insertion position information of the pilot control rod does not meet the preset pilot control rod insertion position information conditions, the exchange of insertion order of each control rod in the target control rod group is temporarily suspended. Based on the insertion position information of the pilot control rod, the pilot control rod is either lifted or inserted. If the insertion position information of the pilot control rod is less than 50 steps, the pilot control rod is lifted; if the insertion position information of the pilot control rod is greater than 150 steps, the pilot control rod is inserted, until the insertion position information of the pilot control rod meets the preset pilot control rod insertion position information conditions, that is, until the target control rod group meets the first order exchange condition.
[0046] Optionally, the control rod sequence exchange condition includes a second sequence exchange condition; the method for determining whether the target control rod group meets the second sequence exchange condition is as follows: determine the temperature control rod and its insertion position information in the target control rod group; determine whether the temperature control rod insertion position information meets the preset temperature control rod insertion position information condition based on the temperature control rod insertion position information; if the preset temperature control rod insertion position information condition is met, then the target control rod group is determined to meet the second sequence exchange condition.
[0047] Among them, the temperature control rod can be a control rod that controls the operating temperature of the nuclear power core in real time when the control rods in the target control rod group need to be exchanged sequentially. This is to avoid the nuclear power core's operating efficiency and safety being affected when the control capability of the nuclear power core decreases due to the sequential exchange of insertion positions in the target rod group.
[0048] Specifically, the second sequential exchange condition can be to determine whether the insertion position information of the temperature control rods in the target control rod group meets the preset temperature control rod insertion position information conditions. Specifically, after obtaining the temperature control rods and their insertion position information in the target control rod group, the insertion position information of the temperature control rods can be compared with the preset temperature control rod insertion position information conditions to obtain a position information comparison result; based on the position information comparison result, it can be determined whether the target control rods meet the second sequential exchange condition. More specifically, it can be done by determining the distance information between the temperature control rods and the nuclear power core, and comparing it with the preset distance information conditions between the temperature control rods and the nuclear power core. For example, if the distance information between the temperature control rods and the nuclear power core is found to be 200 steps, and the preset distance information conditions between the temperature control rods and the nuclear power core can be 165-255 steps, then it can be determined that the insertion position information of the temperature control rods meets the preset temperature control rod insertion position information conditions, that is, the target control rod group meets the second sequential exchange condition. This embodiment does not impose specific limitations on this.
[0049] Optionally, the control rod sequence exchange condition includes a third sequence exchange condition; the method for determining whether the target control rod group meets the third sequence exchange condition is as follows: based on the real-time operating power of the target nuclear power reactor core and the insertion position information of the pilot control rod, determine whether the real-time operating power of the target nuclear power reactor core meets the preset operating power requirements; if it meets the preset operating power requirements, then determine that the target control rod group meets the third sequence exchange condition.
[0050] The third sequential exchange condition specifically involves determining, based on the pilot control rod insertion position information, whether the real-time operating power of the target nuclear power core meets the power margin requirements during the sequential exchange of control rod insertion positions in the target control rod group. The power margin requirements can specifically include baseline peak line heating rate requirements and heat pipe factor limitations. Specifically, this refers to the additional control capability the control rod group possesses to manage the nuclear power core's operation during the sequential exchange of control rod insertion positions, and can be pre-set by technicians based on practical experience. If an erroneous alarm of excessive nuclear power core operating power occurs during the sequential exchange of control rods, there may not be sufficient time to take corrective measures. Therefore, before executing the control rod insertion position exchange, it is crucial to ensure that the target control rod group has sufficient power margin to handle potential erroneous alarms of excessive nuclear power core operating power during the exchange, ensuring that the sequential exchange of control rod insertion positions within the target control rod group is completed without exceeding the baseline peak line heating rate and heat pipe factor limitations.
[0051] Specifically, based on the insertion position information of the pilot control rod in the target control rod group, the power margin requirement corresponding to that insertion position information can be obtained. For example, when the insertion position information of the pilot control rod is 50-125 steps, the power margin requirement for the reference peak line heating rate can be 15%, and the power margin requirement for the heat pipe factor limitation can be 3%; when the insertion position information of the pilot control rod is 125-150 steps, the power margin requirement for the reference peak line heating rate can be 10%, and the power margin requirement for the heat pipe factor limitation can be 2%. Furthermore, based on the obtained power margin requirements, the operating power requirements that the target nuclear power reactor core needs to meet can be determined. For example, if the operating power of the nuclear power reactor core is 1000KW and the insertion position information of the pilot control rod is 100 steps, it can be determined that to achieve the heat pipe factor limitation, the control rod group has a power margin of 4%; and to control the heating rate of the nuclear power reactor core to not exceed the baseline peak line, the control rod group has a power margin of 18%. Then it can be determined that the operating power of the target nuclear power reactor core meets the preset operating power requirements, and it can be determined that the target control rod group meets the third sequence exchange condition.
[0052] Optionally, after determining whether the real-time operating power of the target nuclear power reactor core meets the preset operating power requirements based on the real-time operating power of the target nuclear power reactor core and the insertion position information of the pilot control rod, the method further includes: if it is determined that the real-time operating power of the target nuclear power reactor core does not meet the preset operating power requirements, then, based on the insertion position information of the pilot control rod, reducing the real-time operating power of the target nuclear power reactor core to ensure that the real-time operating power of the target nuclear power reactor core meets the preset operating power requirements.
[0053] Specifically, when it is determined that the real-time operating power of the target nuclear power reactor core does not meet the preset operating power requirements, the required power margin can be determined based on the pilot insertion position information. Furthermore, based on the power margin requirements, the real-time operating power of the target nuclear power reactor core can be reduced to meet the preset operating power requirements. For example, if the operating power of the nuclear power reactor core is 1000 kW and the pilot control rod insertion position information is 130 steps, achieving the heat pipe factor limitation requires a 2% power margin, but the current control rod group only has a 1% power margin available, then the operating power of the nuclear power reactor core needs to be reduced by 1% to meet the power margin requirements for performing the control rod insertion position sequence exchange.
[0054] Optionally, the control rod sequence exchange condition includes a fourth sequence exchange condition; the method for determining whether the target control rod group meets the fourth sequence exchange condition is as follows: monitor the operating power of the target nuclear power reactor core and obtain the peak operating power and peak-valley operating power of the target nuclear power reactor core; determine the operating power change value of the target nuclear power reactor core based on the peak operating power and peak-valley operating power; if the operating power change value meets the preset operating power change threshold condition, then it is determined that the target control rod group meets the fourth sequence exchange condition.
[0055] The operating power change threshold condition can be the allowable range of operating power changes during the operation of the nuclear power reactor core. Specifically, it can be preset by technicians based on experience, such as 0-20KW. For example, when the operating power change value meets the operating power change threshold condition, the nuclear power reactor core can be considered to be in a steady-state operating power level, and the insertion order of the control rods can be changed; when the operating power change value does not meet the operating power change threshold condition, the nuclear power reactor core can be considered to be in a dynamic operating power level, and the insertion order of the control rods needs to be temporarily suspended.
[0056] Specifically, during the operation of a nuclear power reactor core, the operating power is not constant and fluctuates. The peak operating power is the highest point of operation during the core's operation; the trough operating power is the lowest point. For example, the peak operating power of the target nuclear power reactor core could be 1005 kW, and the trough operating power could be 995 kW. Furthermore, the difference between the peak and trough operating power can be calculated to obtain the change in operating power of the target nuclear power reactor core, which could be 10 kW. For instance, continuing the previous example, if the threshold condition for the change in operating power is 0-20 kW, and the calculated change in operating power of the target nuclear power reactor core is 10 kW, then the change in operating power of the target nuclear power reactor core meets the pre-set threshold condition, and therefore the target control rod assembly satisfies the fourth sequence exchange condition.
[0057] S130. Determine the sequential exchange execution strategy for the target control rod group based on the current insertion position and the target insertion position.
[0058] The sequential exchange execution strategy can be the execution logic for performing rod lifting and inserting operations on each control rod when the insertion positions of each control rod in the control rod group are sequentially exchanged.
[0059] Specifically, based on the current insertion position and the target insertion position of the target control rod group, the lifting and insertion operations for each control rod in the target control rod group can be determined. For example, the current insertion position sequence of the target control rod group can be position sequence 1: control rod A1-control rod A2-control rod A3-control rod A4, and the target insertion position sequence can be position sequence 2: control rod A4-control rod A3-control rod A2-control rod A1. The execution strategy for the sequential exchange of the target control rod group can be as follows: when lifting control rod A1 in position sequence 1 and raising control rod A1 by a pre-set distance (e.g., 83 steps), then lifting control rod A2, and then lifting control rods A3 and A4 sequentially using the same lifting operation. Furthermore, after completing the lifting operation, the control rod A4 can be inserted. When the control rod A4 is inserted to a fixed distance, such as in step 83, the control rod A3 can be inserted. The same insertion operation is then performed on the control rods A2 and A1 in sequence until the distance between the control rods A4 and A1 meets the preset distance information, such as in step 228. Then, the sequential exchange execution strategy can be determined to be completed.
[0060] S140. According to the sequential exchange execution strategy, the control rods in the target control rod group are sequentially exchanged.
[0061] For example, according to the control rod sequence exchange execution strategy of the target control rod group, the insertion positions of control rods A1 and A4 in the target control rod group can be exchanged in sequence until the distance between control rods A1 and A4 is 228 steps. Further, after the sequence exchange between control rods A1 and A4 is completed, if control rods A2 and A3 are not both fully deployed or fully inserted, their insertion positions can be exchanged in sequence.
[0062] The technical solution of this invention determines the target control rod group that satisfies the current sequential exchange cycle based on the current sequential exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core. If the target control rod group satisfies the preset control rod sequential exchange conditions, the current insertion position of the target control rod group is determined, and the target insertion position is determined based on the current insertion position. A sequential exchange execution strategy for the target control rod group is determined based on the current insertion position and the target insertion position. According to the sequential exchange execution strategy, each control rod in the target control rod group is sequentially exchanged. This embodiment can sequentially exchange each control rod in the control rod group based on the current insertion position and the target insertion position, according to the sequential exchange cycle corresponding to the control rod group in the nuclear power reactor core, and when the control rod group satisfies the preset control rod exchange execution conditions. This prevents excessive burnup shadows from appearing in the fuel containing the control rods, greatly reducing the impact of burnup shadows on the nuclear power reactor core and improving the operating efficiency and safety of the nuclear power reactor core.
[0063] Example 2
[0064] Figure 2 This is a flowchart of a method for sequentially exchanging control rods in a nuclear power reactor core, provided in Embodiment 2 of the present invention. This embodiment further optimizes the method for sequentially exchanging control rods in a nuclear power reactor core based on the above embodiments.
[0065] Furthermore, before the step "determine the target control rod group that satisfies the current sequence exchange cycle based on the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core," add the step "obtain the load operating power and real-time operating power of the target nuclear power reactor core; determine the standard sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core based on the load operating power; determine the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core based on the real-time power, load operating power, and standard sequence exchange cycle." This improves the method for sequentially exchanging the control rods of the nuclear power reactor core. Figure 2 As shown, the method includes:
[0066] S210. Obtain the load operating power and real-time operating power of the target nuclear power reactor core.
[0067] The load operating power can be the theoretical maximum operating power of the nuclear power reactor core, which can be set by technicians based on actual environmental conditions and work experience. The real-time operating power can be the operating power of the nuclear power reactor core in the current time period, specifically the power data collected by existing power detection equipment.
[0068] S220. Based on the load operating power, determine the standard sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core.
[0069] The standard sequence exchange cycle can be the time period for sequentially exchanging the insertion positions of control rods in a nuclear power reactor core at its theoretical maximum operating power, such as 70 days. This standard sequence exchange cycle can be determined by technicians based on the theoretical maximum operating power of the nuclear power reactor core and their practical operational experience.
[0070] S230. Based on the real-time operating power, load operating power, and standard sequence exchange cycle, determine the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core.
[0071] Specifically, the current sequence switching cycle can be calculated proportionally based on the real-time operating power of the nuclear power reactor core and its theoretical maximum operating power. The specific calculation method could be:
[0072] ;
[0073] Where T0 can be the sequential switching cycle of the control rod assembly under the load operating power of the nuclear power reactor core, i.e., the standard sequential switching cycle; P avg It can be the real-time operating power of the nuclear power reactor core; T t This can be the sequential exchange cycle of the control rod assembly under the real-time operating power of the nuclear power reactor core, i.e., the current sequential exchange cycle. Specifically, when the nuclear power reactor core operates at a power level lower than the load operating power for an extended period, the sequential exchange cycle of at least one control rod in the nuclear power reactor core can be proportionally extended to the reciprocal of the real-time operating power to ensure the burnup balance of the fuel assembly where the control rod is located and reduce the generation of burnup shadows.
[0074] S240. Determine the target control rod group that satisfies the current sequence exchange cycle based on the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core.
[0075] S250. If it is determined that the target control rod group meets the preset control rod sequence exchange conditions, then the current insertion position of the target control rod group is determined, and the target insertion position is determined based on the current insertion position.
[0076] S260. Determine the sequential exchange execution strategy for the target control rod group based on the current insertion position and the target insertion position.
[0077] S270. According to the sequential exchange execution strategy, the control rods in the target control rod group are sequentially exchanged.
[0078] The technical solution of this invention obtains the load operating power and real-time operating power of the target nuclear power reactor core; determines the standard sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core based on the load operating power; and determines the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core based on the real-time operating power, load operating power, and standard sequence exchange cycle. This technical solution can determine the current sequence exchange cycle of the target control rod group based on the real-time operating power, load operating power, and the standard sequence exchange cycle of the corresponding target control rod group, thereby realizing the sequential exchange of the insertion positions of each control rod in the target control rod group. This achieves automated exchange of the insertion positions of each control rod in the control rod group, improving the operating efficiency and safety of the nuclear power reactor core. Simultaneously, it prevents excessive burnup shadows in the fuel containing the control rods, reducing the impact of burnup shadows on the nuclear power reactor core.
[0079] Example 3
[0080] Figure 3 This is a schematic diagram of a control rod sequential exchange device for a nuclear power reactor core provided in Embodiment 3 of the present invention. The control rod sequential exchange device for a nuclear power reactor core provided in this embodiment of the present invention is applicable to situations where the operating efficiency of the nuclear power reactor core is significantly reduced and safety is low during the sequential exchange of control rods. The control rod sequential exchange device can be implemented in hardware and / or software, such as… Figure 3 As shown, it specifically includes: a control rod group acquisition module 310, an insertion position determination module 320, a sequential exchange execution strategy determination module 330, and a sequential exchange execution module 340. Among them,
[0081] The control rod group acquisition module 310 is used to determine the target control rod group that satisfies the current sequence exchange cycle based on the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core.
[0082] The insertion position determination module 320 is used to determine the current insertion position of the target control rod group if it is determined that the target control rod group meets the preset control rod sequence exchange conditions, and to determine the target insertion position based on the current insertion position.
[0083] The sequential exchange execution strategy determination module 330 is used to determine the sequential exchange execution strategy of the target control rod group based on the current insertion position and the target insertion position of the target control rod group;
[0084] The sequential exchange execution module 340 is used to control the sequential exchange of each control rod in the target control rod group according to the sequential exchange execution strategy.
[0085] This embodiment can be based on the sequential exchange cycle of the control rod group in the nuclear power reactor core. When the control rod group meets the preset control rod exchange execution conditions, the control rods in the control rod group are sequentially exchanged according to the current insertion position and the target insertion position of the control rod group. This prevents excessive fuel burn-out shadows in the control rods, greatly reduces the impact of burn-out shadows on the nuclear power reactor core, and improves the operating efficiency and safety of the nuclear power reactor core.
[0086] Optionally, the device may also include a sequential exchange condition judgment module;
[0087] Optional, the order swap condition judgment module includes:
[0088] The first sequence exchange condition judgment unit is used to determine whether the control rod sequence exchange condition includes a first sequence exchange condition; the method for judging whether the target control rod group satisfies the first sequence exchange condition is as follows:
[0089] Determine the pilot control rod in the target control rod group and the insertion position information of the pilot control rod;
[0090] Based on the insertion position information of the pilot control rod, determine whether it meets the preset conditions for the insertion position information of the pilot control rod;
[0091] If the pre-set pilot rod insertion position information condition is met, then the target control rod group is determined to satisfy the first sequence exchange condition.
[0092] The second sequence exchange condition judgment unit is used to determine whether the control rod sequence exchange condition includes a second sequence exchange condition; the method for judging whether the target control rod group satisfies the second sequence exchange condition is as follows:
[0093] Determine the temperature control rods in the target control rod group and the insertion position information of the temperature control rods;
[0094] Based on the insertion position information of the temperature control rod, determine whether it meets the preset temperature control rod insertion position information conditions;
[0095] If the preset temperature control rod insertion position information conditions are met, then the target control rod group is determined to satisfy the second sequence exchange condition;
[0096] The third sequence exchange condition judgment unit is used to determine whether the control rod sequence exchange condition includes a third sequence exchange condition; the method for judging whether the target control rod group meets the third sequence exchange condition is as follows:
[0097] Based on the real-time operating power of the target nuclear power reactor core and the insertion position information of the pilot control rod, determine whether the real-time operating power of the target nuclear power reactor core meets the preset operating power requirements;
[0098] If the preset operating power requirements are met, then the target control rod group is determined to satisfy the third sequence exchange condition.
[0099] Optionally, the device further includes: an operating power adjustment module, configured to, after determining whether the real-time operating power of the target nuclear power reactor core meets the preset operating power requirements based on the real-time operating power of the target nuclear power reactor core and the insertion position information of the pilot control rod, reduce the real-time operating power of the target nuclear power reactor core according to the insertion position information of the pilot control rod, so as to ensure that the real-time operating power of the target nuclear power reactor core meets the preset operating power requirements.
[0100] Optionally, the device further includes: a sequence exchange cycle acquisition module, used to acquire the load operating power and real-time operating power of the target nuclear power reactor core before determining the target control rod group that satisfies the current sequence exchange cycle based on the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core;
[0101] Based on the load operating power, determine the standard sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core;
[0102] Based on the real-time operating power, the load operating power, and the standard sequence exchange cycle, determine the current sequence exchange cycle corresponding to at least one control rod group of the target nuclear power reactor core.
[0103] The control rod sequence exchange device for nuclear power reactor cores provided in this embodiment of the invention can execute the control rod sequence exchange method for nuclear power reactor cores provided in any embodiment of the invention, and has the corresponding functional modules and beneficial effects of the method.
[0104] Example 4
[0105] Figure 4A schematic diagram of an electronic device 40 that can be used to implement embodiments of the present invention is shown. The electronic device is intended to represent various forms of digital computers, such as laptop computers, desktop computers, workstations, personal digital assistants, servers, blade servers, mainframe computers, and other suitable computers. The electronic device can also represent various forms of mobile devices, such as personal digital processors, cellular phones, smartphones, wearable devices (e.g., helmets, glasses, watches, etc.), and other similar computing devices. The components shown herein, their connections and relationships, and their functions are merely illustrative and are not intended to limit the implementation of the invention described and / or claimed herein.
[0106] like Figure 4 As shown, the electronic device 40 includes at least one processor 41 and a memory, such as a read-only memory (ROM) 42 or a random access memory (RAM) 43, communicatively connected to the at least one processor 41. The memory stores computer programs executable by the at least one processor. The processor 41 can perform various appropriate actions and processes based on the computer program stored in the ROM 42 or loaded from storage unit 48 into the RAM 43. The RAM 43 may also store various programs and data required for the operation of the electronic device 40. The processor 41, ROM 42, and RAM 43 are interconnected via a bus 44. An input / output (I / O) interface 45 is also connected to the bus 44.
[0107] Multiple components in electronic device 40 are connected to I / O interface 45, including: input unit 46, such as keyboard, mouse, etc.; output unit 47, such as various types of monitors, speakers, etc.; storage unit 48, such as disk, optical disk, etc.; and communication unit 49, such as network card, modem, wireless transceiver, etc. Communication unit 49 allows electronic device 40 to exchange information / data with other devices through computer networks such as the Internet and / or various telecommunications networks.
[0108] Processor 41 can be a variety of general-purpose and / or special-purpose processing components with processing and computing capabilities. Some examples of processor 41 include, but are not limited to, a central processing unit (CPU), a graphics processing unit (GPU), various special-purpose artificial intelligence (AI) computing chips, various processors running machine learning model algorithms, a digital signal processor (DSP), and any suitable processor, controller, microcontroller, etc. Processor 41 performs the various methods and processes described above, such as the control rod sequential exchange method in a nuclear power reactor core.
[0109] In some embodiments, the nuclear power core control rod sequential exchange method can be implemented as a computer program tangibly contained in a computer-readable storage medium, such as storage unit 48. In some embodiments, part or all of the computer program can be loaded and / or installed on electronic device 40 via ROM 42 and / or communication unit 49. When the computer program is loaded into RAM 43 and executed by processor 41, one or more steps of the nuclear power core control rod sequential exchange method described above can be performed. Alternatively, in other embodiments, processor 41 can be configured to perform the nuclear power core control rod sequential exchange method by any other suitable means (e.g., by means of firmware).
[0110] Various embodiments of the systems and techniques described above herein can be implemented in digital electronic circuit systems, integrated circuit systems, field-programmable gate arrays (FPGAs), application-specific integrated circuits (ASICs), application-specific standard products (ASSPs), systems-on-a-chip (SoCs), payload-programmable logic devices (CPLDs), computer hardware, firmware, software, and / or combinations thereof. These various embodiments may include implementations in one or more computer programs that can be executed and / or interpreted on a programmable system including at least one programmable processor, which may be a dedicated or general-purpose programmable processor, capable of receiving data and instructions from a storage system, at least one input device, and at least one output device, and transmitting data and instructions to the storage system, the at least one input device, and the at least one output device.
[0111] Computer programs used to implement the methods of the present invention may be written in any combination of one or more programming languages. These computer programs may be provided to a processor of a general-purpose computer, a special-purpose computer, or other programmable data processing device, such that when executed by the processor, the computer programs cause the functions / operations specified in the flowcharts and / or block diagrams to be performed. The computer programs may be executed entirely on a machine, partially on a machine, or as a standalone software package, partially on a machine and partially on a remote machine, or entirely on a remote machine or server.
[0112] In the context of this invention, a computer-readable storage medium can be a tangible medium that may contain or store a computer program for use by or in conjunction with an instruction execution system, apparatus, or device. A computer-readable storage medium may include, but is not limited to, electronic, magnetic, optical, electromagnetic, infrared, or semiconductor systems, apparatus, or devices, or any suitable combination thereof. Alternatively, a computer-readable storage medium may be a machine-readable signal medium. More specific examples of machine-readable storage media include electrical connections based on one or more wires, portable computer disks, hard disks, random access memory (RAM), read-only memory (ROM), erasable programmable read-only memory (EPROM or flash memory), optical fibers, portable compact disk read-only memory (CD-ROM), optical storage devices, magnetic storage devices, or any suitable combination thereof.
[0113] To provide interaction with a user, the systems and techniques described herein can be implemented on an electronic device having: a display device (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor) for displaying information to the user; and a keyboard and pointing device (e.g., a mouse or trackball) through which the user provides input to the electronic device. Other types of devices can also be used to provide interaction with the user; for example, feedback provided to the user can be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user can be received in any form (including sound input, voice input, or tactile input).
[0114] The systems and technologies described herein can be implemented in computing systems that include backend components (e.g., as data servers), or middleware components (e.g., application servers), or frontend components (e.g., user computers with graphical user interfaces or web browsers through which users can interact with implementations of the systems and technologies described herein), or any combination of such backend, middleware, or frontend components. The components of the system can be interconnected via digital data communication of any form or medium (e.g., communication networks). Examples of communication networks include local area networks (LANs), wide area networks (WANs), blockchain networks, and the Internet.
[0115] A computing system can include clients and servers. Clients and servers are generally located far apart and typically interact through communication networks. The client-server relationship is created by computer programs running on the respective computers and having a client-server relationship with each other. The server can be a cloud server, also known as a cloud computing server or cloud host, which is a hosting product within the cloud computing service system. It addresses the shortcomings of traditional physical hosts and VPS (Virtual Private Server) services, such as high management difficulty and weak business scalability.
[0116] It should be understood that the various forms of processes shown above can be used, with steps reordered, added, or deleted. For example, the steps described in this invention can be executed in parallel, sequentially, or in different orders, as long as the desired result of the technical solution of this invention can be achieved, and this is not limited herein.
[0117] The specific embodiments described above do not constitute a limitation on the scope of protection of this invention. Those skilled in the art should understand that various modifications, combinations, sub-combinations, and substitutions can be made according to design requirements and other factors. Any modifications, equivalent substitutions, and improvements made within the spirit and principles of this invention should be included within the scope of protection of this invention.
Claims
1. A method of control rod sequential exchange for a nuclear reactor core, characterized by, The method comprises the following steps: determining a target control rod group that meets a current sequence exchange period corresponding to at least one control rod group of a target nuclear reactor core according to the current sequence exchange period corresponding to the at least one control rod group of the target nuclear reactor core; if it is determined that the target control rod group meets a preset control rod sequence exchange condition, determining a current insertion position of the target control rod group and determining a target insertion position according to the current insertion position; determining a sequence exchange execution strategy of the target control rod group according to the current insertion position and the target insertion position of the target control rod group; controlling the sequence exchange of each control rod in the target control rod group according to the sequence exchange execution strategy.
2. The method of claim 1, wherein, The control rod sequence exchange condition comprises a first sequence exchange condition; and the determination of whether the target control rod group meets the first sequence exchange condition is as follows: determining a leading control rod in the target control rod group and insertion position information of the leading control rod; determining whether a preset leading control rod insertion position information condition is met according to the insertion position information of the leading control rod; if the preset leading control rod insertion position information condition is met, it is determined that the target control rod group meets the first sequence exchange condition.
3. The method of claim 1, wherein, The control rod sequence exchange condition comprises a second sequence exchange condition; and the determination of whether the target control rod group meets the second sequence exchange condition is as follows: determining a temperature control rod in the target control rod group and insertion position information of the temperature control rod; determining whether a preset temperature control rod insertion position information condition is met according to the insertion position information of the temperature control rod; if the preset temperature control rod insertion position information condition is met, it is determined that the target control rod group meets the second sequence exchange condition.
4. The method of claim 1, wherein, The control rod sequence exchange condition comprises a third sequence exchange condition; and the determination of whether the target control rod group meets the third sequence exchange condition is as follows: determining whether a preset operation power requirement is met according to a real-time operation power of the target nuclear reactor core and based on the insertion position information of the leading control rod; if the preset operation power requirement is met, it is determined that the target control rod group meets the third sequence exchange condition.
5. The method of claim 4, wherein, After the determination of whether the preset operation power requirement is met according to the real-time operation power of the target nuclear reactor core and based on the insertion position information of the leading control rod, the method further comprises the following step: if it is determined that the real-time operation power of the target nuclear reactor core does not meet the preset operation power requirement, reducing the real-time operation power of the target nuclear reactor core according to the insertion position information of the leading control rod to ensure that the real-time operation power of the target nuclear reactor core meets the preset operation power requirement.
6. The method of claim 1, wherein, Before the determination of the target control rod group that meets the current sequence exchange period corresponding to at least one control rod group of a target nuclear reactor core according to the current sequence exchange period corresponding to the at least one control rod group of the target nuclear reactor core, the method further comprises the following steps: obtaining a load operation power and a real-time operation power of the target nuclear reactor core; According to the load operation power, a standard sequence exchange period corresponding to at least one control rod bank of the target nuclear power core is determined; According to the real-time operation power, the load operation power and the standard sequence exchange period, a current sequence exchange period corresponding to at least one control rod bank of the target nuclear power core is determined.
7. A control rod sequential exchange device for a nuclear reactor core, characterized by, The method comprises the steps of: A control rod bank acquisition module is configured to determine a target control rod bank satisfying a current sequence exchange period of at least one control rod bank of a target nuclear power core according to the current sequence exchange period of the control rod bank; An insertion position determination module is configured to determine a current insertion position of the target control rod bank if it is determined that the target control rod bank satisfies a preset control rod sequence exchange condition, and determine a target insertion position according to the current insertion position; A sequence exchange execution strategy determination module is configured to determine a sequence exchange execution strategy of the target control rod bank according to the current insertion position and the target insertion position of the target control rod bank; A sequence exchange execution module is configured to control the sequence exchange of each control rod in the target control rod bank according to the sequence exchange execution strategy.
8. An electronic device, comprising: The electronic device comprises: at least one processor; and a memory connected to the at least one processor in communication; wherein The memory stores a computer program executed by the at least one processor, and the computer program is executed by the at least one processor to enable the at least one processor to execute the control rod sequence exchange method of the nuclear power core according to any one of claims 1-6.
9. A computer-readable storage medium, characterized in that, The computer readable storage medium stores computer instructions for enabling the processor to execute the control rod sequence exchange method of the nuclear power core according to any one of claims 1-6.
10. A computer program product, characterised in that, The computer program product comprises a computer program, and the computer program is executed by the processor to implement the control rod sequence exchange method of the nuclear power core according to any one of claims 1-6.
Citation Information
Patent Citations
Rod changing system and method for control rod of nuclear power plant reactor
CN106531236A
Rod changing system and method for reactor of nuclear power plant
CN117012412A
Pressurized water reactor rod changing method and system, electronic equipment and computer readable storage medium
CN119650123A
Process for power control of a nuclear power plant in load-following operation
DE102017205553A1
Reactor core condition estimator
JP1989260400A