CN111584106B - Nuclear power station fuel unit substitution method, device, equipment and storage medium - Google Patents
Nuclear power station fuel unit substitution method, device, equipment and storage medium Download PDFInfo
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- CN111584106B CN111584106B CN202010306133.7A CN202010306133A CN111584106B CN 111584106 B CN111584106 B CN 111584106B CN 202010306133 A CN202010306133 A CN 202010306133A CN 111584106 B CN111584106 B CN 111584106B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/205—Interchanging of fuel elements in the core, i.e. fuel shuffling
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention relates to the technical field of a nuclear power station primary loop reactor, and provides a nuclear power station fuel unit substitution method, a device, equipment and a storage medium. The method comprises the steps of obtaining first fuel information of an initial fuel unit which is currently operated by a nuclear power plant core by receiving a nuclear power plant core fuel replacement instruction, and confirming whether the initial fuel unit contains a first fuel consumption assembly and/or a second fuel consumption assembly which needs to be replaced or not according to the first fuel information; when the initial fuel unit is confirmed to contain the first fuel consumption assembly and/or the second fuel consumption assembly, second fuel information of the assembly to be replaced is obtained; and determining a replacement fuel consumption assembly from the assemblies to be replaced according to the first fuel information and the second fuel information, and replacing the first fuel consumption assembly and/or the second fuel consumption assembly in the initial fuel unit with the replacement fuel consumption assembly to obtain the replacement fuel unit. By the method, the combustible poison amount and the residual combustible poison amount are reduced, the fuel utilization rate is improved, and the design cycle length is prolonged.
Description
Technical Field
The invention relates to the technical field of a nuclear power station primary loop reactor, in particular to a nuclear power station fuel unit substitution method, a device, equipment and a storage medium.
Background
In the operation management of a nuclear power plant, the safety and the economy of operation are often taken as important consideration factors, and on the basis of ensuring the safety of a reactor core of the nuclear power plant, the utilization rate of fuel should be improved as much as possible so as to improve the economy of the operation of the nuclear power plant.
At present, in core refueling management design, nuclear power plants generally design the natural circulation length (end-of-life critical boron concentration of 10ppm) within the range of ± 5EFPD of the power generation plan requirements. Under the design mode, the problems of low fuel utilization rate and low economical efficiency exist from the average unloading fuel consumption data of the nuclear power station. In the prior art, a large project needs to be improved, a brand-new fuel management strategy is adopted, fuel assemblies are changed in type, and FSAR accidents need to be analyzed again, system equipment is demonstrated, field reconstruction is needed, and the like. However, the scheme has long project duration, high input cost and high facing technical risk.
Disclosure of Invention
The embodiment of the invention provides a method, a device, equipment and a storage medium for replacing a fuel unit of a nuclear power station, which are used for solving the problem of low fuel utilization rate.
In order to solve the above problems, the present invention provides a nuclear power plant fuel unit substitution method, which includes:
receiving a fuel replacement instruction of a nuclear power plant core, acquiring first fuel information of an initial fuel unit which is currently operated by the nuclear power plant core, and confirming whether the initial fuel unit contains a first fuel consumption assembly and/or a second fuel consumption assembly which need to be replaced or not according to the first fuel information; the first burnup assembly is a burnup assembly comprising 20 gadolinium-containing rods, and the second burnup assembly is a burnup assembly comprising 24 gadolinium-containing rods;
when the initial fuel unit is confirmed to contain a first fuel consumption assembly and/or a second fuel consumption assembly, second fuel information of the assembly to be replaced is obtained; wherein the number of gadolinium-containing rods of the component to be replaced is less than the number of gadolinium-containing rods of the first fuel consumption component and the second fuel consumption component;
and determining a substitute fuel assembly from the assemblies to be replaced according to the first fuel information and the second fuel information, and replacing the first fuel assembly and/or the second fuel assembly in the initial fuel unit with the substitute fuel assembly to obtain a substitute fuel unit.
The invention provides a replacing device of a fuel unit of a nuclear power station, which comprises:
the replacement instruction receiving module is used for receiving a fuel replacement instruction of the nuclear power plant core, acquiring first fuel information of an initial fuel unit which is currently operated by the nuclear power plant core, and confirming whether the initial fuel unit comprises a first fuel consumption assembly and/or a second fuel consumption assembly which needs to be replaced or not according to the first fuel information; the first burnup assembly is a burnup assembly comprising 20 gadolinium-containing rods, and the second burnup assembly is a burnup assembly comprising 24 gadolinium-containing rods;
the fuel information acquisition module is used for acquiring second fuel information of the component to be replaced when the initial fuel unit is confirmed to contain the first fuel consumption component and/or the second fuel consumption component; wherein the number of gadolinium-containing rods of the component to be replaced is less than the number of gadolinium-containing rods of the first fuel consumption component and the second fuel consumption component;
and the alternative fuel consumption component determining module is used for determining an alternative fuel consumption component from the components to be replaced according to the first fuel information and the second fuel information, and replacing the first fuel consumption component and/or the second fuel consumption component in the initial fuel unit with the alternative fuel consumption component to obtain an alternative fuel unit.
The replacement method, the device, the equipment and the storage medium of the nuclear power plant fuel unit provided by the invention have the advantages that the first fuel information of the initial fuel unit currently operated by the nuclear power plant core is obtained by receiving the fuel replacement instruction of the nuclear power plant core, and whether the initial fuel unit contains a first fuel consumption assembly and/or a second fuel consumption assembly to be replaced is determined according to the first fuel information; the first burnup assembly is a burnup assembly comprising 20 gadolinium-containing rods, and the second burnup assembly is a burnup assembly comprising 24 gadolinium-containing rods; when the initial fuel unit is confirmed to contain the first fuel consumption assembly and/or the second fuel consumption assembly, second fuel information of the assembly to be replaced is obtained; the number of gadolinium-containing rods of the component to be replaced is less than that of gadolinium-containing rods of the first fuel consumption component and the second fuel consumption component; and determining a replacement fuel consumption assembly from the assemblies to be replaced according to the first fuel information and the second fuel information, and replacing the first fuel consumption assembly and/or the second fuel consumption assembly in the initial fuel unit with the replacement fuel consumption assembly to obtain the replacement fuel unit. According to the invention, the first burnup assembly and/or the second burnup assembly with more gadolinium rods are/is replaced by selecting the burnup assemblies with less gadolinium rods, so that the amount of combustible toxins in a fuel unit of the nuclear power station is reduced, the residual quantity of the combustible toxins is reduced, the fuel utilization rate is improved, and the design cycle length is prolonged.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the embodiments or the prior art descriptions will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without inventive exercise.
FIG. 1 is a flow chart of an alternative method for a nuclear power plant fuel assembly in accordance with an embodiment of the present invention;
FIG. 2 is another flow chart of an alternative method for a nuclear power plant fuel assembly in accordance with an embodiment of the present invention;
FIG. 3 is a flowchart of step S13 of the method for replacing a nuclear power plant fuel assembly according to an embodiment of the present invention;
FIG. 4 is another flow chart of an alternative method for a nuclear power plant fuel assembly in accordance with an embodiment of the present invention;
FIG. 5 is a schematic block diagram of a nuclear power plant fuel assembly replacement apparatus according to an embodiment of the present invention;
FIG. 6 is another schematic block diagram of an alternative arrangement for a nuclear power plant fuel assembly in accordance with an embodiment of the present invention;
FIG. 7 is a functional block diagram of an alternative burnup component determination module of an alternative apparatus for a nuclear power plant fuel assembly in accordance with an embodiment of the present invention;
fig. 8 is another schematic block diagram of a nuclear power plant fuel assembly replacement apparatus according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, not all, embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
An embodiment of the present invention provides a method for replacing a nuclear power plant fuel assembly, as shown in fig. 1, including the following steps:
s11: receiving a fuel replacement instruction of a nuclear power plant core, acquiring first fuel information of an initial fuel unit which is currently operated by the nuclear power plant core, and determining whether the initial fuel unit contains a first fuel consumption component and/or a second fuel consumption component which need to be replaced or not according to the first fuel information; the first burnup assembly was a burnup assembly comprising 20 gadolinium containing rods and the second burnup assembly was a burnup assembly comprising 24 gadolinium containing rods.
The nuclear power plant core fuel replacement instruction refers to an instruction for replacing a fuel-consuming component in a fuel unit of a nuclear power plant, and can be a voice prompt, an interface text display prompt or an information prompt or other effective prompt instructions. The first fuel information refers to the number of burnup assemblies corresponding to the same number of gadolinium-containing rods in the initial fuel assembly. For example, the first fuel information may be that the number of burnup assemblies including 0 gadolinium-containing rods in the initial fuel assembly group is 6, the number of burnup assemblies including 8 gadolinium-containing rods is 12, the number of burnup assemblies including 20 gadolinium-containing rods is 12, or the number of burnup assemblies including 24 gadolinium-containing rods is 16, and so on. The first burnup assembly was a burnup assembly comprising 20 gadolinium containing rods in the initial fuel assembly. The second fuel assembly was a fuel assembly comprising 24 gadolinium containing rods in the initial fuel assembly.
Specifically, after a fuel replacement instruction of the nuclear power plant core is received, first fuel information of an initial fuel unit in which the nuclear power plant core is currently operating is acquired, and the first fuel information indicates the number of burnup components corresponding to the same number of gadolinium-containing rods in the initial fuel unit. (ii) a Further, it is determined whether the initial fuel assembly contains 20 first burnup assemblies containing gadolinium rods and/or 24 second burnup assemblies containing gadolinium rods according to the first fuel information.
S12: when the initial fuel unit is confirmed to contain the first fuel consumption assembly and/or the second fuel consumption assembly, second fuel information of the assembly to be replaced is obtained; wherein the number of gadolinium-containing rods of the component to be replaced is less than the number of gadolinium-containing rods of the first and second burnup components.
The number of the gadolinium-containing rods of the component to be replaced is less than that of the gadolinium-containing rods of the first fuel consumption component and the second fuel consumption component, and the component to be replaced can be a fuel consumption component comprising 16 gadolinium-containing rods or a fuel consumption component comprising 4 gadolinium-containing rods. The second fuel information refers to the number of components to be replaced corresponding to the same number of gadolinium containing rods.
Specifically, after first fuel information of an initial fuel unit currently operated by a nuclear power plant core is acquired, when it is determined that the initial fuel unit contains a first burnup component and/or a second burnup component, acquiring the number of components to be replaced corresponding to the same number of gadolinium-containing rods, that is, acquiring second fuel information of the components to be replaced. Further, the number of gadolinium-containing rods of the to-be-replaced assembly is smaller than that of the gadolinium-containing rods of the first fuel consumption assembly and the second fuel consumption assembly. Illustratively, the number of gadolinium containing rods of a burnup assembly comprising 16 gadolinium containing rods is less than the number of gadolinium containing rods of the first burnup assembly, and less than the number of gadolinium containing rods of the second burnup assembly, 24.
S13: and determining a replacement fuel consumption assembly from the assemblies to be replaced according to the first fuel information and the second fuel information, and replacing the first fuel consumption assembly and/or the second fuel consumption assembly in the initial fuel unit with the replacement fuel consumption assembly to obtain the replacement fuel unit.
Wherein the replacement burnup assembly is for replacing the first burnup assembly and/or the second burnup replacement assembly. The alternative fuel assembly is obtained after replacement of a portion of the consumable components of the original fuel machine.
Specifically, when the initial fuel unit is confirmed to contain a first fuel consumption assembly and/or a second fuel consumption assembly, after second fuel information of the assemblies to be replaced is obtained, the number of the first fuel consumption assembly and/or the second fuel consumption assembly which need to be replaced is determined according to the first fuel information, the number of the fuel consumption assemblies to be replaced which can be replaced is determined according to the second fuel consumption information, and the replacement fuel consumption assembly is confirmed from the fuel consumption assemblies to be replaced which can be replaced. And after the alternative fuel assemblies are confirmed, replacing the first fuel assemblies and/or the second fuel assemblies in the initial fuel unit with the alternative fuel assemblies to obtain the alternative fuel unit.
In the embodiment, the burnup assemblies with a small number of gadolinium-containing rods are selected and replaced, so that the amount of combustible toxins in a fuel unit of the nuclear power station is reduced, the residual amount of the combustible toxins is reduced, the fuel utilization rate is improved, and the design cycle length is prolonged.
In an embodiment, as shown in fig. 2, before step S12, that is, before acquiring the second fuel information of the component to be replaced, the method further includes the following steps:
s21: and acquiring an information record table of the stock burnup components, wherein the information record table contains the number of gadolinium-containing rods corresponding to each stock burnup component.
The stock burnup components are the rest of the stored burnup components, and the stock burnup components comprise burnup components with different numbers of gadolinium-containing rods. And the information recording table is used for recording fuel information of the stock burnup assemblies and comprises the number of gadolinium-containing rods corresponding to each stock burnup assembly.
S22: and detecting whether the quantity of gadolinium-containing rods of the stock burnup assemblies is less than that of the gadolinium-containing rods of the first burnup assembly and the second burnup assembly, and simultaneously detecting whether the stock burnup assemblies meet the universality requirement.
Wherein, the universality requirement refers to that the stock fuel consumption assembly meets the operation requirement of the fuel unit.
Specifically, after an information recording table of the stock burnup components is obtained, whether the number of gadolinium-containing rods of the stock burnup components is smaller than the number of gadolinium-containing rods of a first burnup component and a second burnup component is detected according to the information recording table; and if the burnup assemblies with the quantity of gadolinium-containing rods smaller than that of the first burnup assembly and the second burnup assembly exist in the stock burnup assemblies, detecting the universality of all the stock burnup assemblies with the quantity of gadolinium-containing rods smaller than that of the first burnup assembly and the second burnup assembly, namely confirming that the stock burnup assemblies have no influence or influence on the operation of the core safety and the fuel unit but have influence within a safety threshold.
S23: and when the quantity of the gadolinium-containing rods of the stock burnup assembly is less than that of the gadolinium-containing rods of the first burnup assembly and the second burnup assembly, and the stock burnup assembly meets the universality requirement, determining the stock burnup assembly as the assembly to be replaced.
Specifically, after detecting whether the number of gadolinium-containing rods of the stock burnup assemblies is smaller than the number of gadolinium-containing rods of the first burnup assembly and the second burnup assembly and detecting whether the stock burnup assemblies meet the universality requirement, if the stock burnup assemblies with the number of gadolinium-containing rods smaller than the number of gadolinium-containing rods of the first burnup assembly and the second burnup assembly exist and the stock burnup assemblies meet the universality requirement, the stock burnup assemblies are determined as assemblies to be replaced.
In one embodiment, as shown in fig. 3, the step S13 of determining a replacement fuel-consuming component from the components to be replaced according to the first fuel information and the second fuel information includes the following steps:
s131: determining the number of first fuel consumption components and/or second fuel consumption components to be replaced in the initial fuel unit according to the first fuel information;
wherein the number to be replaced refers to the total number of the first and/or second consumable assemblies.
Specifically, after first fuel information of an initial fuel unit currently operated by a nuclear power plant core is acquired, the total number of first burnup components and/or second burnup components in the initial fuel unit is determined according to the first fuel information, so as to confirm the number to be replaced corresponding to the burnup components needing to be replaced.
S132: and acquiring the number of the components to be replaced according to the second fuel information.
Specifically, after the second fuel information of the component to be replaced is acquired, the number of components to be replaced that are available for replacement is determined based on the second fuel information.
S133: and if the number of the components to be replaced is one, determining the components to be replaced as the replaced burnup components.
Specifically, after acquiring the number of components to be replaced from the second fuel information, if there is one and only one component to be replaced, the component to be replaced is identified as a replacement consumable component.
S134: and if the number of the assemblies to be replaced is more than two, determining the number of the replaced burnup assemblies consistent with the number to be replaced from all the assemblies to be replaced according to a preset selection rule.
The preset selection rule can be selected from small to large according to the character string sequence corresponding to the name of the component to be replaced, and can also be selected according to a random selection rule.
Specifically, after acquiring the number of components to be replaced from the second fuel information, if the number of components to be replaced exceeds two, the substitute burnup components of which the number is identical to the number to be replaced are determined from all the components to be replaced according to a preset selection rule.
Further, if the number of components to be replaced is less than the number to be replaced, all components to be replaced are replaced by the same number of first and/or second consumable components. The remaining first and/or second consumable components that are not replaced are not modified.
Preferably, when the number of assemblies to be replaced is equal to or greater than the number to be replaced, it may be determined whether all or part of the first and/or second burnup assemblies will be replaced according to the cycle length requirement and the core power distribution, moderator temperature coefficient, etc.
In one embodiment, as shown in fig. 4, after step S13, that is, after replacing the initial fuel assembly with a replacement fuel assembly, the method includes:
s31: and acquiring key safety parameters of the alternative fuel consumption assembly and key safety parameters of the specific accident.
The key safety parameters are reactor core physical and thermal hydraulic parameters which influence the normal operation or transient characteristics of the reactor core and the development result of the accident condition by replacing a fuel-consuming assembly. The key safety parameters of the specific accident are specific accident parameters which are used for replacing the fuel-consuming assemblies and are influenced by the installation of the reactor core, and the key safety parameters are mainly reactive accidents.
S32: and acquiring an FSAR (Final Safety Analysis Report) Safety Analysis Report of the initial fuel unit.
The FSAR safety analysis report is a safety analysis report obtained by performing stack entering test and analysis on an initial fuel unit.
S33: and after verifying that the safety of the alternative fuel unit is correct according to the key safety parameters, the key safety parameters of the specific accident and the safety limit values reported by the FSAR safety analysis, replacing the initial fuel unit with the alternative fuel unit.
Wherein, the safety refers to that the key safety parameters of the substitute fuel consumption component and the key safety parameters of the specific accident are less than the safety limit value reported by the FSAR safety analysis.
Specifically, after key safety parameters and specific accident key safety parameters of the alternative fuel assemblies are acquired and an FSAR safety analysis report of the initial fuel unit is acquired, the key safety parameters and the specific accident key safety parameters are compared with safety limits in the FSAR safety analysis report to determine whether the key safety parameters and the specific accident key safety parameters are less than the safety limits in the FSAR safety analysis report. If the key safety parameters and the specific accident key safety parameters are smaller than the safety limit values in the FSAR safety analysis report, the key safety parameters and the specific accident key safety parameters do not break through the enveloping range of the FASR, and more detailed accident analysis is not needed. Meanwhile, when the key safety parameters and the key safety parameters of the specific accident are smaller than the safety limit values in the FSAR safety analysis report, the safety of the alternative fuel unit is determined to be correct, and the initial fuel unit is replaced by the alternative fuel unit.
In this embodiment, the safety limit reported by the FSAR safety analysis of the initial fuel assembly is compared to the critical safety parameters of the replacement fuel assemblies and the critical safety parameters of the specific accident. By adopting the method, when the key safety parameters and the key safety parameters of the specific accident are smaller than the safety limit value reported by the FSAR safety analysis, the safety of the alternative fuel unit can be confirmed, a large amount of work load of the reactor core safety accident analysis is reduced, and the reactor core refueling efficiency is improved.
In an embodiment, after step S13, that is, after replacing the initial fuel assembly with the replacement fuel assembly, the method further includes:
and when the alternative fuel unit is in stack operation, acquiring a boron concentration value of the alternative fuel unit in the operation process.
And when the boron concentration value reaches a preset shutdown threshold value, if the boron concentration value is detected to be within the range of the preset shutdown threshold value, performing extended operation on the alternative fuel unit.
The preset shutdown threshold refers to a threshold for stopping the operation of a reactor component of the nuclear power station, and is measured by a boron concentration value, and may be 10 ppm. The preset trip threshold range may be 9-11 ppm.
Specifically, after the alternative fuel unit is obtained, the alternative fuel unit is put into a reactor to operate, a boron concentration value in the operation process of the alternative fuel unit is monitored, and when the boron concentration value is 10ppm and the preset reactor shutdown threshold value range is 9-11ppm, namely the current boron concentration value reaches the preset reactor shutdown threshold value, the alternative fuel unit is subjected to extension operation. When the boron concentration value exceeds 11ppm, the alternative fuel unit continues to operate in a reactor; when the boron concentration value is lower than 9ppm, the operation of the alternative fuel unit is finished within a certain time by carrying out the extension operation.
Further, the performing an extended run operation on the alternative fuel assembly may include:
and reducing the temperature of the moderator by increasing the opening of the steam inlet regulating valve of the steam turbine, further keeping the steam inlet regulating valve of the steam turbine fully opened, and increasing the flow of the main steam to reduce the temperature of the moderator. This can be achieved by reducing the reactor power of the reactor assembly.
Preferably, before the alternative fuel unit is put into the stack for operation, the cycle length requirement corresponding to the alternative fuel unit is acquired. During the reactor core fuel management design, the cycle length of actual operation is shortened, so that in the process of putting the alternative fuel unit into the reactor for operation, if the boron concentration value reaches the preset shutdown threshold value and the boron concentration value reaching the preset shutdown threshold value is still within the range of the preset shutdown threshold value, the alternative fuel unit is required to be subjected to extended operation, thus the fuel utilization rate can be improved, and the number of new assemblies for next refueling and piling is reduced.
In the embodiment, the number of refueling and stacking new assemblies is reduced while the fuel utilization rate is improved by performing extended operation on the alternative fuel unit.
It should be understood that, the sequence numbers of the steps in the foregoing embodiments do not imply an execution sequence, and the execution sequence of each process should be determined by its function and inherent logic, and should not constitute any limitation to the implementation process of the embodiments of the present invention.
In an embodiment, a replacement device for a fuel unit of a nuclear power plant is provided, and the replacement device for the fuel unit of the nuclear power plant corresponds to the replacement method for the fuel unit of the nuclear power plant in the embodiment one to one. As shown in fig. 5, the replacement device for a fuel assembly of a nuclear power plant includes a replacement instruction receiving module 11, a fuel information acquiring module 12, and a replacement burnup component determining module 13. The functional modules are explained in detail as follows:
the replacement instruction receiving module 11 is configured to receive a fuel replacement instruction of a nuclear power plant core, acquire first fuel information of an initial fuel unit currently operating in the nuclear power plant core, and determine whether the initial fuel unit includes a first fuel assembly and/or a second fuel assembly to be replaced according to the first fuel information; the first burnup assembly is a burnup assembly comprising 20 gadolinium-containing rods, and the second burnup assembly is a burnup assembly comprising 24 gadolinium-containing rods;
the fuel information acquisition module 12 is configured to acquire second fuel information of a component to be replaced when it is determined that the initial fuel unit includes a first consumable component and/or a second consumable component; wherein the number of gadolinium-containing rods of the component to be replaced is less than the number of gadolinium-containing rods of the first fuel consumption component and the second fuel consumption component;
and the alternative fuel consumption component determining module 13 is configured to determine an alternative fuel consumption component from the components to be replaced according to the first fuel information and the second fuel information, and replace the first fuel consumption component and/or the second fuel consumption component in the initial fuel unit with the alternative fuel consumption component to obtain an alternative fuel unit.
Preferably, as shown in fig. 6, the fuel assembly replacement apparatus for a nuclear power plant further includes:
the information record table acquisition module 21 is configured to acquire an information record table of the stock burnup assemblies, where the information record table includes the number of gadolinium-containing rods corresponding to each stock burnup assembly;
an inventory burnup component detection module 22, configured to detect whether the number of gadolinium-containing rods of the inventory burnup component is smaller than the number of gadolinium-containing rods of the first burnup component and the second burnup component, and detect whether the inventory burnup component meets the requirement for universality;
and the to-be-replaced assembly confirming module 23 is used for confirming the stock burnup assembly as the to-be-replaced assembly when the quantity of the gadolinium-containing rods of the stock burnup assembly is less than that of the gadolinium-containing rods of the first burnup assembly and the second burnup assembly and the stock burnup assembly meets the universality requirement.
Preferably, as shown in fig. 7, the alternative burnup component determination module 13 further includes:
a to-be-replaced number determining unit 131, configured to determine, according to the first fuel information, a to-be-replaced number of first fuel assemblies and/or second fuel assemblies to be replaced in the initial fuel assembly;
a number-of-components-to-be-replaced acquiring unit 132 for acquiring the number of components to be replaced based on the second fuel information;
a first replacement consumable component identifying unit 133 for identifying a replacement consumable component among the components to be replaced when the number of the components to be replaced is one;
the second alternative burnup component determining unit 134 is configured to determine, according to a preset selection rule, alternative burnup components of which the number is consistent with the number to be replaced from all the components to be replaced when the number of the components to be replaced is more than two.
Preferably, as shown in fig. 8, the nuclear power plant fuel assembly replacement apparatus further includes:
the safety parameter acquisition module 31 is used for acquiring key safety parameters of the alternative fuel consuming unit and key safety parameters of a specific accident;
a safety analysis report obtaining module 32, configured to obtain an FSAR safety analysis report of the initial fuel unit;
and the safety verification module 33 is configured to, after verifying that the safety of the alternative burnup component is correct according to the key safety parameters, the key safety parameters of the specific accident and the safety limit values in the FSAR safety analysis report, replace the initial fuel unit with the alternative burnup component.
Preferably, the nuclear power plant fuel assembly replacement device further comprises:
the system comprises a boron concentration value acquisition unit, a control unit and a control unit, wherein the boron concentration value acquisition unit is used for acquiring a boron concentration value of an alternative fuel unit in the operation process when the alternative fuel unit is in stack operation;
and the extension operation unit is used for carrying out extension operation on the alternative fuel unit if the detected boron concentration value is within the range of the preset shutdown threshold value when the boron concentration value reaches the preset shutdown threshold value.
For specific definition of the replacement device for the fuel unit of the nuclear power plant, reference may be made to the above definition of the replacement method for the fuel unit of the nuclear power plant, and details are not described herein again. All or part of each module in the nuclear power plant fuel unit substituting device can be realized by software, hardware and a combination thereof. The modules can be embedded in a hardware form or independent from a processor in the computer device, and can also be stored in a memory in the computer device in a software form, so that the processor can call and execute operations corresponding to the modules.
In one embodiment, a computer device is provided, which includes a memory, a processor, and a computer program stored on the memory and executable on the processor, and when the processor executes the computer program, the method for replacing the fuel assembly of the nuclear power plant in the above embodiments is implemented.
In one embodiment, a computer-readable storage medium is provided, having a computer program stored thereon, which, when executed by a processor, implements the nuclear power plant fuel assembly replacement method of the above-described embodiments.
It will be understood by those skilled in the art that all or part of the processes of the methods of the embodiments described above can be implemented by hardware instructions of a computer program, which can be stored in a non-volatile computer-readable storage medium, and when executed, can include the processes of the embodiments of the methods described above. Any reference to memory, storage, database, or other medium used in the embodiments provided herein may include non-volatile and/or volatile memory, among others. Non-volatile memory can include read-only memory (ROM), Programmable ROM (PROM), Electrically Programmable ROM (EPROM), Electrically Erasable Programmable ROM (EEPROM), or flash memory. Volatile memory can include Random Access Memory (RAM) or external cache memory. By way of illustration and not limitation, RAM is available in a variety of forms such as Static RAM (SRAM), Dynamic RAM (DRAM), Synchronous DRAM (SDRAM), Double Data Rate SDRAM (DDRSDRAM), Enhanced SDRAM (ESDRAM), Synchronous Link DRAM (SLDRAM), Rambus Direct RAM (RDRAM), direct bus dynamic RAM (DRDRAM), and memory bus dynamic RAM (RDRAM).
It will be apparent to those skilled in the art that, for convenience and brevity of description, only the above-mentioned division of the functional units and modules is illustrated, and in practical applications, the above-mentioned function distribution may be performed by different functional units and modules according to needs, that is, the internal structure of the apparatus is divided into different functional units or modules to perform all or part of the above-mentioned functions.
The above-mentioned embodiments are only used for illustrating the technical solutions of the present invention, and not for limiting the same; although the present invention has been described in detail with reference to the foregoing embodiments, it will be understood by those of ordinary skill in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some technical features may be equivalently replaced; such modifications and substitutions do not substantially depart from the spirit and scope of the embodiments of the present invention, and are intended to be included within the scope of the present invention.
Claims (10)
1. A nuclear power plant fuel unit replacement method is characterized by comprising the following steps:
receiving a nuclear power station reactor core fuel replacement instruction, acquiring first fuel information of an initial fuel unit currently operated by the nuclear power station, and confirming whether the initial fuel unit contains a first fuel consumption assembly and/or a second fuel consumption assembly to be replaced or not according to the first fuel information; the first burnup assembly is a burnup assembly comprising 20 gadolinium-containing rods, and the second burnup assembly is a burnup assembly comprising 24 gadolinium-containing rods; the first fuel information refers to the number of burnup assemblies corresponding to the same number of gadolinium-containing rods in the initial fuel unit;
when the initial fuel unit is confirmed to contain a first fuel consumption assembly and/or a second fuel consumption assembly, second fuel information of the assembly to be replaced is obtained; wherein the number of gadolinium-containing rods of the component to be replaced is less than the number of gadolinium-containing rods of the first fuel consumption component and the second fuel consumption component; the second fuel information refers to the number of components to be replaced corresponding to the same number of gadolinium-containing rods;
determining a substitute fuel consumption assembly from the assemblies to be replaced according to the first fuel information and the second fuel information, and replacing the first fuel consumption assembly and/or the second fuel consumption assembly in the initial fuel unit with the substitute fuel consumption assembly to obtain a substitute fuel unit;
the determining a replacement consumable component from the components to be replaced according to the first fuel information and the second fuel information, further comprising:
determining the quantity to be replaced of a first fuel consumption assembly and/or a second fuel consumption assembly which needs to be replaced in the initial fuel unit according to the first fuel information;
acquiring the number of the components to be replaced according to the second fuel information;
if the number of the components to be replaced is one, confirming the components to be replaced as the replaced burnup components;
and if the number of the assemblies to be replaced is more than two, determining the number of the replaced burnup assemblies consistent with the number to be replaced from all the assemblies to be replaced according to a preset selection rule.
2. The nuclear power plant fuel assembly replacement method according to claim 1, wherein before acquiring the second fuel information of the component to be replaced, the method further comprises:
acquiring an information record table of the stock burnup components, wherein the information record table contains the number of gadolinium-containing rods corresponding to each stock burnup component;
detecting whether the quantity of gadolinium-containing rods of a stock burnup assembly is less than the quantity of gadolinium-containing rods of the first burnup assembly and the second burnup assembly, and simultaneously detecting whether the stock burnup assembly meets the universality requirement;
and when the quantity of the gadolinium-containing rods of the stock burnup assembly is less than that of the gadolinium-containing rods of the first burnup assembly and the second burnup assembly, and the stock burnup assembly meets the universality requirement, determining the stock burnup assembly as an assembly to be replaced.
3. The nuclear power plant fuel assembly replacement method as recited in claim 1, wherein the replacing the first burnup component and/or the second burnup component in the initial fuel assembly with the replacement burnup component further comprises, after obtaining a replacement fuel assembly:
acquiring key safety parameters of the alternative fuel unit and key safety parameters of a specific accident;
obtaining an FSAR safety analysis report of the initial fuel unit;
and according to the key safety parameters, the key safety parameters of the specific accident and the safety limit values in the FSAR safety analysis report, after verifying that the safety of the alternative fuel unit is correct, replacing the initial fuel unit with the alternative fuel unit.
4. The nuclear power plant fuel assembly replacement method according to claim 1, wherein the replacing the first consumable component and/or the second consumable component to be replaced in the initial fuel assembly with the replacement consumable component further comprises:
when the alternative fuel unit is in stack operation, acquiring a boron concentration value in the operation process of the alternative fuel unit;
and when the boron concentration value reaches a preset shutdown threshold value, if the boron concentration value is detected to be within a preset shutdown threshold value range, performing extended operation on the alternative fuel unit.
5. A nuclear power plant fuel assembly substitution device, characterized by comprising:
the replacement instruction receiving module is used for receiving a fuel replacement instruction of the nuclear power plant core, acquiring first fuel information of an initial fuel unit which is currently operated by the nuclear power plant core, and confirming whether the initial fuel unit comprises a first fuel consumption assembly and/or a second fuel consumption assembly which needs to be replaced or not according to the first fuel information; the first burnup assembly is a burnup assembly comprising 20 gadolinium-containing rods, and the second burnup assembly is a burnup assembly comprising 24 gadolinium-containing rods; the first fuel information refers to the number of burnup assemblies corresponding to the same number of gadolinium-containing rods in the initial fuel unit;
the fuel information acquisition module is used for acquiring second fuel information of the component to be replaced when the initial fuel unit is confirmed to contain the first fuel consumption component and/or the second fuel consumption component; wherein the number of gadolinium-containing rods of the component to be replaced is less than the number of gadolinium-containing rods of the first fuel consumption component and the second fuel consumption component; the second fuel information refers to the number of components to be replaced corresponding to the same number of gadolinium-containing rods;
the alternative fuel consumption component determining module is used for determining an alternative fuel consumption component from the components to be replaced according to the first fuel information and the second fuel information, and replacing the first fuel consumption component and/or the second fuel consumption component in the initial fuel unit with the alternative fuel consumption component to obtain an alternative fuel unit;
the alternative burnup component determination module includes:
the number-to-be-replaced determining unit is used for determining the number of the first fuel assemblies and/or the second fuel assemblies to be replaced in the initial fuel unit according to the first fuel information;
a to-be-replaced component number acquisition unit configured to acquire the number of the to-be-replaced components according to the second fuel information;
a first replacement consumable component identifying unit configured to identify a replacement consumable component among the components to be replaced when the number of the components to be replaced is one;
and the second alternative burnup component confirmation unit is used for determining alternative burnup components with the same number as the number to be replaced from all the assemblies to be replaced according to a preset selection rule when the number of the assemblies to be replaced is more than two.
6. The nuclear power plant fuel assembly replacement device of claim 5, further comprising:
the information record table acquisition module is used for acquiring an information record table of the stock burnup components, and the information record table contains the number of gadolinium-containing rods corresponding to each stock burnup component;
the stock burnup component detection module is used for detecting whether the number of gadolinium-containing rods of the stock burnup components is less than the number of gadolinium-containing rods of the first burnup component and the second burnup component, and simultaneously detecting whether the stock burnup components meet the universality requirement;
and the to-be-replaced assembly confirming module is used for confirming the stock burnup assembly as the to-be-replaced assembly when the quantity of the gadolinium-containing rods of the stock burnup assembly is less than the quantity of the gadolinium-containing rods of the first burnup assembly and the second burnup assembly and the stock burnup assembly meets the universality requirement.
7. The nuclear power plant fuel assembly replacement device of claim 5, further comprising:
the safety parameter acquisition unit is used for acquiring key safety parameters of the alternative fuel consuming unit and key safety parameters of specific accidents;
the safety analysis report acquisition unit is used for acquiring an FSAR safety analysis report of the initial fuel unit;
and the safety verification unit is used for replacing the initial fuel unit with the alternative fuel unit after verifying that the safety of the alternative fuel unit is correct according to the key safety parameters, the key safety parameters of the specific accident and the safety limit values in the FSAR safety analysis report.
8. The nuclear power plant fuel assembly replacement device of claim 5, further comprising:
the system comprises a boron concentration value acquisition unit, a control unit and a control unit, wherein the boron concentration value acquisition unit is used for acquiring a boron concentration value of an alternative fuel unit in the operation process when the alternative fuel unit is operated in a stack;
and the extension operation unit is used for carrying out extension operation on the alternative fuel unit when the boron concentration value reaches a preset shutdown threshold value and if the boron concentration value is detected to be within a preset shutdown threshold value range.
9. A computer arrangement comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor, when executing the computer program, implements the nuclear power plant fuel assembly replacement method as claimed in any one of claims 1 to 4.
10. A computer-readable storage medium, in which a computer program is stored, which, when being executed by a processor, carries out a method for replacing a nuclear power plant fuel assembly according to any one of claims 1 to 4.
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