Irradiation supervision method and device, terminal equipment and computer program product

Abstract

The invention is suitable for the technical field of safety assessment of reactor pressure vessels of nuclear power plants, and provides an irradiation supervision method and device, terminal equipment and a computer program product.The method is applied to a reactor pressure vessel and comprises the steps that a target unit is determined according to judgment conditions of multi-unit linkage irradiation supervision; making an irradiation supervision plan of the target unit; and obtaining and outputting irradiation supervision data of the target unit according to the irradiation supervision plan. According to the embodiment of the invention, aiming at the condition that the number of irradiation supervision samples of a single-unit reactor pressure vessel during in-service operation is small, but a large number of units of the same model exist, the multi-unit linkage irradiation supervision plan is established, so that multi-unit linkage irradiation supervision is realized, and the reliability of irradiation supervision is effectively improved.

Description

Technical Field

[0001] This application belongs to the technical field of safety assessment of reactor pressure vessels in nuclear power plants, and particularly relates to a radiation supervision method, device, terminal device, and computer program product. Background Art

[0002] The reactor pressure vessel (RPV) is one of the most critical devices in a nuclear power plant, and it is crucial for ensuring the safe operation of the nuclear power plant. Since it serves in a strong radiation, high-temperature, and high-pressure environment for a long time, in order to ensure the safety of the reactor pressure vessel during operation, radiation supervision is required.

[0003] The existing radiation supervision methods can only achieve radiation supervision during the in-service operation of the reactor pressure vessel of a single unit. Moreover, when the radiation supervision specimens in the reactor pressure vessel of this unit are all extracted, the reactor pressure vessel of this unit will face the situation of having no radiation supervision specimens for radiation supervision. Therefore, it is necessary to provide a new radiation supervision method to overcome the limitations of the existing radiation supervision methods and improve the reliability of radiation supervision. Summary of the Invention

[0004] In view of this, the embodiments of this application provide a radiation supervision method, device, terminal device, and computer program product to solve the problem that the existing radiation supervision methods can only achieve radiation supervision during the in-service operation of the reactor pressure vessel of a single unit.

[0005] The first aspect of the embodiments of this application provides a radiation supervision method, which is applied to a reactor pressure vessel. The method includes:

[0006] Determine a target unit according to the determination conditions for multi-unit linked radiation supervision;

[0007] Formulate a radiation supervision plan for the target unit;

[0008] Obtain and output the radiation supervision data of the target unit according to the radiation supervision plan.

[0009] In one embodiment, the determining a target unit according to the determination conditions for multi-unit linked radiation supervision includes:

[0010] Establish the determination conditions for multi-unit linked radiation supervision;

[0011] Obtain the information of the target nuclear power plant, and determine the nuclear power unit that meets the determination conditions in the target nuclear power plant as the target unit.

[0012] In one embodiment, the establishing the determination conditions for multi-unit linked radiation supervision includes:

[0013] Establish any one or several of a first determination condition based on reactor structure design parameters, a second determination condition based on core and fuel management mode parameters, and a third determination condition based on material parameters of the reactor pressure vessel.

[0014] In one embodiment, the reactor structure design parameters include a variety of parameters such as the inner diameter of the core barrel, water gap, active section height, design pressure, design temperature, operating pressure, overall height of the reactor pressure vessel, outlet temperature of the reactor pressure vessel, inlet temperature of the reactor pressure vessel, and the material of the in-core components;

[0015] The core and fuel management mode parameters include a variety of parameters such as core rated power, core thermal power, core layout shape, fuel assembly type, number of fuel assemblies, refueling cycle, number of control rods, and control rod layout;

[0016] The material parameters of the reactor pressure vessel include a variety of parameters such as the chemical composition of the material of the reactor pressure vessel, initial mechanical properties, and irradiation embrittlement model.

[0017] In one embodiment, formulating the irradiation supervision plan for the target unit includes:

[0018] Determine a preset number of irradiation supervision specimens in the target unit;

[0019] Formulate an irradiation supervision cycle.

[0020] In one embodiment, obtaining and outputting the irradiation supervision data of the target unit according to the irradiation supervision plan includes:

[0021] Extract a plurality of target irradiation supervision specimens that meet the irradiation supervision cycle from the preset number of irradiation supervision specimens;

[0022] Detect the plurality of target irradiation supervision specimens to obtain and output the irradiation supervision data of the plurality of target irradiation supervision specimens.

[0023] In one embodiment, formulating the irradiation supervision cycle includes:

[0024] Formulate a plurality of the irradiation supervision cycles;

[0025] Correspondingly, obtaining and outputting the irradiation supervision data of the target unit according to the irradiation supervision plan includes:

[0026] Extract a plurality of target irradiation supervision specimens that meet each of the irradiation supervision cycles from the preset number of irradiation supervision specimens;

[0027] Detect multiple target irradiation supervision specimens for multiple irradiation supervision cycles, obtain irradiation supervision data of the multiple target irradiation supervision specimens, and output the data.

[0028] A second aspect of the embodiments of the present application provides an irradiation supervision device applied to a reactor pressure vessel. The device includes:

[0029] A target determination module for determining a target unit according to the determination conditions of multi-unit linked irradiation supervision;

[0030] A plan formulation module for formulating an irradiation supervision plan for the target unit;

[0031] A data acquisition module for acquiring and outputting irradiation supervision data of the target unit according to the irradiation supervision plan.

[0032] A third aspect of the embodiments of the present application provides a terminal device, including a memory, a processor, and a computer program stored in the memory and executable on the processor. When the processor executes the computer program, the steps of the irradiation supervision method described in the first aspect of the embodiments of the present application are implemented.

[0033] A fourth aspect of the embodiments of the present application provides a computer program product. The computer program product includes a computer program, and when the computer program is executed by a processor, the steps of the irradiation supervision method described in the first aspect of the embodiments of the present application are implemented.

[0034] The irradiation supervision method provided in the first aspect of the embodiments of the present application is applied to a reactor pressure vessel. According to the determination conditions of multi-unit linked irradiation supervision, a target unit is determined; an irradiation supervision plan for the target unit is formulated; and irradiation supervision data of the target unit is acquired and output according to the irradiation supervision plan. In view of the situation that there are few irradiation supervision specimens for a single-unit reactor pressure vessel during in-service operation, but there are a large number of units of the same type, by establishing a multi-unit linked irradiation supervision plan, multi-unit linked irradiation supervision is realized, effectively improving the reliability of irradiation supervision.

[0035] It can be understood that the beneficial effects of the above second aspect to the fourth aspect can be referred to the relevant descriptions in the above first aspect, and will not be elaborated here. BRIEF DESCRIPTION OF THE DRAWINGS

[0036] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the following will briefly introduce the drawings required for use in the embodiments or the description of the prior art. Obviously, the following drawings are only some embodiments of the present application. For those of ordinary skill in the art, other drawings can be obtained based on these drawings without creative efforts.

[0037] Figure 1 It is the first schematic flow chart of the irradiation supervision method provided by the embodiments of the present application;

[0038] Figure 2 It is the second schematic flow chart of the irradiation supervision method provided by the embodiments of the present application;

[0039] Figure 3 It is the schematic diagram of the irradiation embrittlement model of the materials in the core area of the reactor pressure vessel under different neutron fluence conditions provided by the embodiments of the present application;

[0040] Figure 4 It is the schematic structural diagram of the irradiation supervision device provided by the embodiments of the present application;

[0041] Figure 5 It is the schematic structural diagram of the terminal device provided by the embodiments of the present application. Detailed implementation manners

[0042] In the following description, specific details such as specific system structures and technologies are presented for the purpose of illustration rather than limitation, so as to thoroughly understand the embodiments of the present application. However, those skilled in the art should clearly understand that the present application can also be implemented in other embodiments without these specific details. In other cases, detailed descriptions of well-known systems, devices, circuits, and methods are omitted to avoid unnecessary details from interfering with the description of the present application.

[0043] It should also be understood that the term "and / or" used in the specification and appended claims of the present application refers to any combination and all possible combinations of one or more of the related listed items, and includes these combinations.

[0044] In addition, in the description of the specification and appended claims of the present application, the terms "first", "second", "third", etc. are only used for distinguishing descriptions and cannot be understood as indicating or implying relative importance.

[0045] The reference to "one embodiment" or "some embodiments" etc. described in the specification of the present application means that a specific feature, structure, or characteristic described in connection with the embodiment is included in one or more embodiments of the present application. Thus, the statements "in one embodiment", "in some embodiments", "in other some embodiments", "in still other embodiments", etc. that appear in different places in this specification do not necessarily refer to the same embodiment, but mean "one or more but not all embodiments", unless otherwise specifically emphasized in other ways. The terms "comprise", "include", "have" and their variants all mean "including but not limited to", unless otherwise specifically emphasized in other ways. "Multiple" means "two" or "more than two".

[0046] The reactor pressure vessel is one of the most critical equipment in a nuclear power plant and is crucial for ensuring the safe operation of the nuclear power plant. Since it serves in a high-irradiation, high-temperature, and high-pressure environment for a long time, in order to ensure the safety of the reactor pressure vessel during operation, irradiation supervision is required.

[0047] Existing irradiation supervision methods can only achieve irradiation supervision of the reactor pressure vessel of a single unit during its in-service operation. Moreover, when the irradiation supervision specimens in the reactor pressure vessel of this unit are all extracted, the reactor pressure vessel of this unit will face the situation of having no irradiation supervision specimens for irradiation supervision. Therefore, it is necessary to provide a new irradiation supervision method to overcome the limitations of existing irradiation supervision methods and improve the reliability of irradiation supervision.

[0048] The embodiment of the present application provides an irradiation supervision method applied to a reactor pressure vessel. According to the determination conditions for multi-unit linked irradiation supervision, the target unit is determined; an irradiation supervision plan for the target unit is formulated; and according to the irradiation supervision plan, the irradiation supervision data of the target unit is obtained and output. In view of the situation that there are few irradiation supervision specimens for the reactor pressure vessel of a single unit during in-service operation but there are a large number of units of the same model, by establishing a multi-unit linked irradiation supervision plan, multi-unit linked irradiation supervision is realized, effectively improving the reliability of irradiation supervision.

[0049] Embodiment 1

[0050] As Figure 1 shown, the irradiation supervision method provided by the embodiment of the present application, which is applied to a reactor pressure vessel, includes the following steps S1 to S3:

[0051] Step S1: According to the determination conditions for multi-unit linked irradiation supervision, determine the target unit and enter step S2.

[0052] In the embodiment of the present application, only the target unit that meets the determination conditions can, by formulating an irradiation supervision plan, further realize multi-unit linked irradiation supervision. Multi-unit linked irradiation supervision means that after the irradiation supervision cycle is met, from a small number of units among the multiple target units that meet the determination conditions combined, irradiation supervision specimens are extracted for testing, and the obtained irradiation supervision data can be used as the irradiation supervision data of each target unit. It can be understood that the target units that meet the determination conditions can be multiple units located in the same nuclear power plant or multiple units in different nuclear power plants, which is not limited here. In addition, the number of target units is not limited in the embodiment of the present application.

[0053] In one embodiment, as Figure 2 shown, step S1 includes the following steps S11 to S12:

[0054] Step S11: Establish the determination conditions for multi-unit linked irradiation supervision, and enter step S12.

[0055] In applications, even for multiple units located in the same nuclear power plant, it may not be possible to achieve multi-unit linked irradiation supervision due to differences in the reactor structure design or the materials of the reactor pressure vessels of each unit. Similarly, even for multiple units located in different nuclear power plants, it may be possible to achieve multi-unit linked irradiation supervision because they have the same or nearly the same reactor structure design or the same or nearly the same materials of the reactor pressure vessels. Based on this, the embodiments of the present application establish the following determination conditions to determine whether multi-unit linked irradiation supervision can be achieved between the units located in the same nuclear power plant or different nuclear power plants.

[0056] In applications, when establishing the determination conditions, existing operating experience of reactor pressure vessels or irradiation damage data, etc. can be referred to improve the accuracy and reliability of the determination conditions.

[0057] In one embodiment, step S11 specifically includes:

[0058] Establish any one or several of the first determination condition based on reactor structure design parameters, the second determination condition based on core and fuel management mode parameters, and the third determination condition based on the material parameters of the reactor pressure vessel.

[0059] In applications, the determination conditions can be a combination of any multiple of the first determination condition based on reactor structure design parameters, the second determination condition based on core and fuel management mode parameters, and the third determination condition based on the material parameters of the reactor pressure vessel. In some embodiments, according to different task requirements, the determination conditions can also be any one of the above first determination condition, second determination condition, or third determination condition, which is not limited here.

[0060] In one embodiment, the reactor structure design parameters include multiple of the inner diameter of the core barrel, water gap, active section height, design pressure, design temperature, operating pressure, overall height of the reactor pressure vessel, outlet temperature of the reactor pressure vessel, inlet temperature of the reactor pressure vessel, and the material of the in-core structure;

[0061] The core and fuel management mode parameters include multiple of the core rated power, core thermal power, core layout shape, fuel assembly model, number of fuel assemblies, refueling cycle, number of control rods, and control rod layout;

[0062] The material parameters of the reactor pressure vessel include multiple of the chemical composition, initial mechanical properties, and irradiation embrittlement model of the material of the reactor pressure vessel.

[0063] In an application, the first determination condition based on the reactor structure design parameters includes that the reactor structure design parameters of each unit are the same or nearly the same (the case where the differences between the same design parameters of each unit are very small or even negligible), including but not limited to: the inner diameter of the reactor core barrel (which determines the space size of the core and thus affects the number and arrangement of fuel assemblies), the water gap (the water-filled space between different components of the reactor), the active section height (the height of the part in the core where nuclear fission reactions occur, which is closely related to the design power density of the core), the design pressure (the maximum allowable operating pressure considered during reactor design), the design temperature (the highest allowable temperature considered during reactor design), the operating pressure (the working pressure inside the reactor during actual operation), the overall height of the reactor pressure vessel (including the total length of the entire pressure vessel from the bottom to the top), the outlet temperature of the reactor pressure vessel (the temperature of the coolant when it leaves the reactor core), the inlet temperature of the reactor pressure vessel (the temperature of the coolant before it enters the reactor core), and the materials of the in-core components (such as the materials of fuel assemblies, control rod guide tubes, support structures, etc.). It should be noted that in the embodiments of this application, the specific reactor structure design parameters include but are not limited to any combination of multiple or even all of the above design parameters.

[0064] In an application, the second determination condition based on the core and fuel management mode parameters includes that the core and fuel management mode parameters of each unit are the same or nearly the same (the case where the differences between the same parameters of each unit are very small or even negligible), including but not limited to: the core rated power (the maximum thermal power or electric power that the reactor can continuously output under normal operating conditions), the core thermal power (the total heat generated by fission reactions in the core), the core layout shape (the physical layout of the core), the fuel assembly model (different types of fuel assemblies may have different sizes, fuel enrichments, moderator types, etc. Selecting an appropriate fuel assembly model can optimize the core performance, improve fuel utilization and reduce waste generation), the number of fuel assemblies (the total number of fuel assemblies installed in the core), the refueling cycle (the operating time between two refuelings), the number of control rods (used to adjust the reaction rate of the reactor to ensure safe operation), and the control rod arrangement (the specific position and distribution pattern of the control rods in the core). It should be noted that in the embodiments of this application, the specific core and fuel management mode parameters include but are not limited to any combination of multiple or even all of the above parameters.

[0065] In an application, the third determination condition based on the material parameters of the reactor pressure vessel includes that the material parameters of the reactor pressure vessel of each unit are the same or nearly the same (the case where the differences between the same parameters of each unit are very small or even negligible), including but not limited to: the chemical composition of the material of the reactor pressure vessel, the initial mechanical properties of the material of the reactor pressure vessel, and the irradiation embrittlement model.

[0066] In applications, the chemical composition of the material of the reactor pressure vessel includes, but is not limited to, any combination of carbon (C), manganese (Mn), phosphorus (P), sulfur (S), silicon (Si), nickel (Ni), chromium (Cr), molybdenum (Mo), vanadium (V), copper (Cu), aluminum (Al).

[0067] The initial mechanical properties of the material of the reactor pressure vessel include, but are not limited to, the reference temperature for nil-ductility transition (RTNDT), the upper shelf energy (USE), the yield strength (Rp 0.2 ) at room temperature, the tensile strength (R m ), the elongation (A), the reduction of area (Z), the yield strength (Rp 0.2 ) at high temperature, the tensile strength (R m ), the elongation (A), the reduction of area (Z), and any combination thereof.

[0068] In applications, the reference temperature for nil-ductility transition (RTNDT) is the critical temperature at which the material changes from ductile fracture to brittle fracture. Below this temperature, the material is more prone to brittle fracture, while above this temperature, the material exhibits good ductility.

[0069] In applications, the upper shelf energy (USE) is the maximum absorbed energy value of the material in an impact test at high temperature or room temperature, which can be measured by the Charpy impact test. USE is used to evaluate the impact toughness of the material under normal operating conditions to ensure that the material can maintain good impact resistance at high temperatures. A higher USE value indicates better ductility of the material.

[0070] In applications, the tensile strength (R m ) at room temperature or high temperature, R m is the maximum stress that the material can withstand during a tensile test at room temperature or high temperature. R m is used to measure the load-bearing capacity of the material at room temperature to ensure that the RPV will not fracture due to external forces under normal operating conditions. A higher R m value means that the material has higher strength.

[0071] In applications, the yield strength (Rp 0.2) Rp0.2 refers to the stress borne by a material when it undergoes a tensile test at room temperature or high temperature and produces 0.2% plastic deformation. It is the critical point at which the material begins to undergo permanent deformation. Rp0.2 is used to evaluate the anti-plastic deformation ability of the material at room temperature or high temperature to ensure that the RPV does not undergo irreversible deformation under normal operating conditions. A higher Rp0.2 value means that the material has better anti-deformation ability.

[0072] In applications, the elongation (A) at room temperature or high temperature. A refers to the percentage change in length of a material before fracture during a tensile test at room temperature or high temperature. It reflects the ductility of the material. A is used to evaluate the ductility and toughness of the material at room temperature or high temperature to ensure that the material can absorb energy through plastic deformation when subjected to external forces rather than breaking immediately. A higher A value indicates that the material has better ductility.

[0073] In applications, the reduction of area (Z) at room temperature or high temperature. Z refers to the percentage reduction in the cross-sectional area of a specimen after fracture during a tensile test at room temperature or high temperature. It reflects the necking ability and toughness of the material. Z is used to evaluate the toughness and plastic deformation ability of the material at room temperature, especially the local deformation ability of the material before fracture. A higher Z value indicates that the material has better toughness and plasticity.

[0074] In applications, the irradiation embrittlement models of the materials in the core area of the reactor pressure vessel under different neutron fluence conditions are as Figure 3 shown. Among them, RCCM and RSEM are irradiation embrittlement models of French specifications. And RCCM can be used to evaluate the embrittlement behavior of the materials of the reactor pressure vessel caused by neutron irradiation during long-term operation, especially for low-carbon steel and low-alloy steel materials. RSEM can be used to evaluate the embrittlement behavior of the reactor pressure vessel caused by neutron irradiation during long-term operation and can provide a basis for the life extension assessment of the reactor pressure vessel. R.G.1.99 is an irradiation embrittlement model of American specifications, mainly applicable to low-carbon steel and low-alloy steel materials, and is also used to evaluate the embrittlement behavior of the reactor pressure vessel caused by neutron irradiation during long-term operation to provide a basis for the life extension assessment of the reactor pressure vessel. It can be understood that the irradiation embrittlement models of the materials of the reactor pressure vessel in each unit only need to meet one of the above three irradiation embrittlement models.

[0075] It should be noted that in the embodiments of the present application, the specific material parameters of the reactor pressure vessel include, but are not limited to, any combination of the above parameters, even all of them.

[0076] Step S12, obtain the information of the target nuclear power plant and determine the nuclear power units that meet the determination conditions in the target nuclear power plant as the target units.

[0077] In an application, after establishing determination conditions, information of target nuclear power plants (which can be one or more, not limited here) can be collected, various parameter information of each nuclear power unit in each target nuclear power plant can be obtained, and in combination with the determination conditions, units that simultaneously meet the requirements of having the same or nearly the same reactor structure design parameters, the same or nearly the same core and fuel management mode parameters, and the same or nearly the same material parameters of the reactor pressure vessel are selected from multiple units of one nuclear power plant or multiple units of multiple nuclear power plants as target units.

[0078] In some embodiments, when determining target units, in addition to meeting the determination conditions, the following additional determination conditions need to be met among the units:

[0079] The materials in the core area of the reactor pressure vessel are from the same manufacturer and are processed using the same manufacturing process, heat treatment system, etc.;

[0080] The materials and raw materials of the fuel assemblies are from the same manufacturer and are processed using the same manufacturing process;

[0081] The same or nearly the same fuel management plan during the expected service life of each unit during in-service operation.

[0082] In some embodiments, the above determination conditions and additional conditions can be combined to screen out the final target units.

[0083] In addition, if there are existing irradiation data of the materials of the in-service reactor pressure vessel (for example, under certain irradiation conditions, defect data (including but not limited to defect data such as dislocation loops and solute clusters) generated by the materials of the reactor pressure vessel and data such as the hardness and tensile strength of the materials), then in step S1, the existing irradiation data can also be collected as the basis for establishing determination conditions or additional determination conditions.

[0084] Step S2: Develop an irradiation supervision plan for the target units and proceed to step S3.

[0085] In an application, when developing an irradiation supervision plan for multi-unit linkage, the following basic principles need to be met:

[0086] The last irradiation supervision specimen of each unit must be extracted when the neutron fluence rate reached by the inner wall of the RPV at the end of the design service life, and if life extension is considered, one specimen must be extracted when the neutron fluence rate reached by the inner wall of the RPV at the end of the life extension period;

[0087] Considering that there is more irradiation data of RPV materials below 40 years currently, the irradiation supervision tubes for multi-unit linkage should be adjusted to be extracted between more than 40 years and the expected life extension;

[0088] Based on the similarity of the design and operation of the same type of units, a certain number of units are set to extract irradiation surveillance specimens every preset period (e.g., 10 years) to predict the irradiation change trend of the entire RPV material of multiple units;

[0089] For the irradiation surveillance of the interlocked operation of each unit, the irradiation surveillance specimens that are initially loaded into the reactor or still in the reactor during the in-service period are used, and spare irradiation surveillance specimens or other reserved irradiation surveillance specimens are not used, so as to reserve conditions for the unit to supplement the subsequent possible irradiation surveillance data or apply for a new license.

[0090] In one embodiment, step S2 specifically includes:

[0091] Determine a preset number of irradiation surveillance specimens in the target unit;

[0092] Formulate an irradiation surveillance cycle.

[0093] In application, when formulating an irradiation surveillance plan, in addition to meeting the above basic principles, it is also necessary to determine the specific data of the irradiation surveillance specimens in each target unit and formulate the corresponding irradiation surveillance cycle. For example, for every 10-year period, one or two irradiation surveillance specimens are extracted from one target unit, or for every 10-year period, one or two irradiation surveillance specimens are extracted from each of the two target units.

[0094] Step S3: Obtain and output the irradiation surveillance data of the target unit according to the irradiation surveillance plan.

[0095] In application, after extracting the corresponding irradiation surveillance specimens according to the irradiation surveillance plan, analyze them to obtain the final irradiation surveillance data. According to actual needs, the obtained irradiation surveillance data can also be output to the user terminal for storage.

[0096] In application, the user terminal includes but is not limited to devices such as mobile phones, tablet computers, wearable devices, augmented reality (AR) / virtual reality (VR) devices, laptop computers, ultra-mobile personal computers (UMPCs), netbooks, and personal digital assistants (PDAs).

[0097] In one embodiment, step S3 specifically includes:

[0098] Extract multiple target irradiation surveillance specimens that meet the irradiation surveillance cycle from the preset number of irradiation surveillance specimens;

[0099] Detect multiple target irradiation surveillance specimens, obtain the irradiation surveillance data of the multiple target irradiation surveillance specimens, and output the data.

[0100] In applications, to avoid data deviation caused by a single specimen, multiple irradiation surveillance specimens can be sampled simultaneously for prediction and analysis, so as to obtain more accurate irradiation surveillance data.

[0101] In one embodiment, step S2 may specifically further include:

[0102] Formulate multiple irradiation surveillance cycles;

[0103] Correspondingly, step S3 may specifically further include:

[0104] From a preset number of irradiation surveillance specimens, extract multiple target irradiation surveillance specimens that meet each irradiation surveillance cycle;

[0105] Detect the multiple target irradiation surveillance specimens for multiple irradiation surveillance cycles, obtain the irradiation surveillance data of the multiple target irradiation surveillance specimens, and output the data.

[0106] In applications, according to different task requirements, when formulating an irradiation surveillance plan, multiple irradiation surveillance cycles can also be formulated simultaneously, and after each irradiation surveillance cycle is met, the corresponding irradiation surveillance specimens are extracted and analyzed, so as to obtain the final irradiation surveillance data. For example, the irradiation surveillance cycles include 10 years, 20 years, 30 years, and 40 years; when the 10-year period is met, one or two irradiation surveillance specimens in one target unit are extracted, or when the 10-year period is met, one or two irradiation surveillance specimens are extracted from each of the two target units; when the 20-year period is met, one or two irradiation surveillance specimens in one target unit are extracted, or when the 20-year period is met, one or two irradiation surveillance specimens are extracted from each of the two target units; when the 30-year period is met, one or two irradiation surveillance specimens in one target unit are extracted, or when the 30-year period is met, one or two irradiation surveillance specimens are extracted from each of the two target units; when the 40-year period is met, one or two irradiation surveillance specimens in one target unit are extracted, or when the 40-year period is met, one or two irradiation surveillance specimens are extracted from each of the two target units.

[0107] It should be noted that in the embodiments of the present application, no specific limitation is imposed on the irradiation surveillance specimens. For example, the irradiation surveillance specimens can be irradiation surveillance tubes or other forms.

[0108] In the embodiments of the present application, by establishing irradiation supervision determination conditions for multi-unit linkage and incorporating nuclear power units that meet these conditions into the irradiation supervision plan for multi-unit linkage, and using the logically sequential irradiation supervision data of each unit, it is possible to achieve joint irradiation supervision among multiple units of a single nuclear power plant or multiple nuclear power plants during in-service operation. Moreover, the irradiation supervision plan for the materials of the reactor pressure vessels that support each other among multiple units not only overcomes the limitations of existing irradiation supervision methods but also improves the reliability of irradiation supervision.

[0109] The content of the present application will be further explained and illustrated through two specific embodiments below, where the irradiation supervision specimen is an irradiation supervision tube.

[0110] (1) There is an existing extraction plan for the irradiation supervision of specimens for in-service irradiation for multi-unit linkage.

[0111] Six million-kilowatt pressurized water reactor RPVs are screened out according to the method of step S1 and numbered. Their design life is 40 years. Among them, 4 units have respectively extracted 4 irradiation supervision tubes (U, V, Z, Y, representing the irradiation embrittlement states of 10, 20, 30, and 40 years respectively), and there are still 2 tubes (W, X) left in the reactor for 80-year life extension. Additionally, 2 units have respectively extracted 3 irradiation supervision tubes (U, V, Z, representing the irradiation embrittlement states of 10, 20, and 30 years respectively), and there are still 3 tubes (Y, S, T) in the reactor for 80-year life extension.

[0112] Since these 6 units meet the above basic principles, it is possible to formulate a joint irradiation supervision plan for these 6 units. The specific plan is shown in the following table:

[0113] Table 1

[0114]

[0115] Table 1 Considering the 80-year life extension of the above 6 units, the last irradiation tube is set to be extracted at the time representing 80 years of service life. For the first 4 units with fewer irradiation tubes, the extraction of the W tube is preferably set at 60 and 70 years to obtain the irradiation supervision embrittlement state under high neutron fluence. For units 5 and 6, first make good use of the existing Y, S, and T tubes in the reactor. Considering that there is more irradiation data at 40 years, the Y tube is adjusted to be extracted at the time representing 50 years, and the S tube is also preferably set at 60 and 70 years to obtain the irradiation supervision embrittlement state under high neutron fluence.

[0116] Therefore, as can be seen from the above table, for the six units, there are at least two sets of irradiation data at 50, 60, and 70 years to support each other regarding the irradiation embrittlement at these time points. However, note that this mutual support of irradiation data is only indirect, used to reflect the irradiation embrittlement trend and approximate change amount of similar units at these time points, and ultimately will be enveloped by the irradiation data of each unit at 80 years.

[0117] In addition, regarding the use of linkage data, taking the irradiation point at 50 years as an example: for the Y pipes of Unit 5 and Unit 6 representing the irradiation at 50 years, they can directly represent the material degradation of their respective RPVs irradiated for 50 years, and can also indirectly predict the RPV irradiation material change trend and approximate change amount of Unit 1, Unit 2, Unit 3, and Unit 4 under 50-year irradiation. Moreover, the irradiation conditions of Unit 2 and Unit 4 at 50 years can be supported by enveloping through their irradiation data at 60 years, and the irradiation conditions of Unit 1 and Unit 3 at 50 years can be supported by enveloping through their irradiation data at 70 years. For the irradiation data points at 60 and 70 years, a similar idea can also be used to support each other to achieve the linkage irradiation supervision of the six units.

[0118] (2) There is no irradiation supervision plan for multi-unit linkage extraction of in-service irradiation supervision pipes.

[0119] Select six million-kilowatt pressurized water reactor RPVs according to the method in Step S1, label them, their designed service life is 60 years, and six irradiation supervision pipes (U, V, Z, Y, S, T, representing the irradiation embrittlement states at 10, 20, 30, 40, 50, and 60 years respectively) are inserted into the reactor. The irradiation supervision pipes have not been extracted yet, and it is necessary to formulate irradiation supervision plans for extending the service life to 80 and 100 years.

[0120] Since these six units meet the above basic principles, an irradiation supervision plan applicable to an 80-year service life for these six units can be formulated. The specific plan is shown in the following table:

[0121] Table 2

[0122]

[0123] Considering that the designed service life of the above six units is 60 years and the service life is extended to 80 and 100 years, irradiation supervision pipe extraction is set at 60, 80, and 100 years. Considering that there is more irradiation data in the first 40 years and the rapid degradation trend in the initial stage of irradiation, for the six units, there are at least two sets of irradiation data at 10, 20, 30, 40, and 50 years to support each other, and there are at least three sets of irradiation data in the first 20 years. Considering the collection of irradiation embrittlement data at high neutron fluence, there are also three sets of irradiation data at 70 and 90 years.

[0124] Therefore, as can be seen from the above table, there is irradiation data of at least 2 tubes for mutual support among the 6 units during 100 years, and key nodes of 60, 80, and 100 years are fully considered, as well as the collection of the rapid degradation trend in the initial stage of irradiation and irradiation embrittlement data at high neutron fluence. For the use of linkage data, refer to the description of the 50-year irradiation data in Example 1.

[0125] As can be seen from the above embodiments, the irradiation supervision method with multi-unit linkage proposed in this application can not only solve the problems of few irradiation supervision tubes for a single unit during the in-service life extension of the RPV, inability to obtain the irradiation change trend of each equivalent irradiation for 10 years, and inability to cope with the irradiation supervision requirements for life extension of 80 years and above; but also realizes the joint irradiation supervision among multi-units of the same model for the first time, uses the irradiation supervision data of multi-units for mutual support, focuses the irradiation supervision tubes on key times such as design life and expected life, and takes into account the rapid degradation trend in the initial stage of RPV irradiation and the collection of irradiation embrittlement data at high neutron fluence, so as to maximize the application effect of the irradiation supervision tubes.

[0126] It should be understood that the magnitudes of the sequence numbers of the steps in the above embodiments do not mean the order of execution. The execution order of each process should be determined according to its function and internal logic, and should not constitute any limitation to the implementation process of the embodiments of this application.

[0127] Embodiment 2

[0128] The embodiment of this application also provides an irradiation supervision device for executing the method steps in the above embodiments of the irradiation supervision method. This device can be a virtual appliance in a terminal device, run by the processor of the terminal device, or the terminal device itself.

[0129] As Figure 4 shown, the irradiation supervision device 100 provided by the embodiment of this application is applied to a reactor pressure vessel, and includes a target determination module 101, a plan formulation module 102, and a data acquisition module 103.

[0130] The target determination module 101 is used to determine the target unit according to the determination conditions of multi-unit linkage irradiation supervision;

[0131] The plan formulation module 102 formulates the irradiation supervision plan for the target unit;

[0132] The data acquisition module 103 is used to obtain and output the irradiation supervision data of the target unit according to the irradiation supervision plan.

[0133] In one embodiment, the target determination module 101 is further used to:

[0134] Establish the determination conditions for multi-unit linkage irradiation supervision;

[0135] Obtain information of the target nuclear power plant, and determine the nuclear power units that meet the determination conditions in the target nuclear power plant as the target units.

[0136] In one embodiment, the target determination module 101 is further configured to:

[0137] Establish any one or several of the first determination condition based on reactor structure design parameters, the second determination condition based on core and fuel management mode parameters, and the third determination condition based on material parameters of the reactor pressure vessel.

[0138] In one embodiment, the reactor structure design parameters include multiple ones among the inner diameter of the core barrel, water gap, active section height, design pressure, design temperature, operating pressure, overall height of the reactor pressure vessel, outlet temperature of the reactor pressure vessel, inlet temperature of the reactor pressure vessel, and the material of the in-core structure;

[0139] The core and fuel management mode parameters include multiple ones among the rated power of the core, core thermal power, core layout shape, fuel assembly model, number of fuel assemblies, refueling cycle, number of control rods, and control rod layout;

[0140] The material parameters of the reactor pressure vessel include multiple ones among the chemical composition of the material of the reactor pressure vessel, initial mechanical properties, and irradiation embrittlement model.

[0141] In one embodiment, the plan formulation module 102 is further configured to:

[0142] Determine a preset number of irradiation surveillance specimens in the target unit;

[0143] Formulate an irradiation surveillance cycle.

[0144] In one embodiment, the data acquisition module 103 is further configured to:

[0145] Extract multiple target irradiation surveillance specimens that meet the irradiation surveillance cycle;

[0146] Detect the multiple target irradiation surveillance specimens, obtain the irradiation surveillance data of the multiple target irradiation surveillance specimens and output them.

[0147] In one embodiment, the plan formulation module 102 is further configured to:

[0148] Formulate multiple irradiation surveillance cycles;

[0149] Correspondingly, the data acquisition module 103 is further configured to:

[0150] Extract multiple target irradiation surveillance specimens that meet each irradiation surveillance cycle;

[0151] Detect multiple target irradiation supervision specimens, obtain the irradiation supervision data of the multiple target irradiation supervision specimens, and output the data.

[0152] In applications, each unit in the above device can be a software program module, can also be implemented by different logic circuits integrated in the processor or independent physical components connected to the processor, and can also be implemented by multiple distributed processors.

[0153] Embodiment III

[0154] As Figure 5 shown, an embodiment of the present application further provides a terminal device 200, including: at least one processor 201 ( Figure 5 only one processor is shown in the figure), a memory 202, and a computer program 203 stored in the memory 202 and operable on at least one processor 201. When the processor 201 executes the computer program 203, the steps in the above method embodiments are implemented.

[0155] In applications, the terminal device includes but is not limited to a processor and a memory. Figure 5 These are only examples of the terminal device and do not limit the terminal device. It may include more or fewer components than shown in the figure, or combine certain components, or different components. For example, a human-computer interaction device, an input / output device, a network access device, etc. The network access device may include a communication module for the terminal device to communicate with a user terminal.

[0156] In applications, the processor may be a central processing unit (CPU), and the processor may also be other general-purpose processors, digital signal processors (DSPs), application specific integrated circuits (ASICs), field-programmable gate arrays (FPGAs), or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. For example, the processor may be a timing controller (TCON). The general-purpose processor may be a microprocessor or the processor may also be any conventional processor, etc.

[0157] In an application, the memory may be an internal storage unit of a terminal device in some embodiments. For example, it may be a hard disk or a memory of the terminal device. In other embodiments, the memory may also be an external storage device of the terminal device. For example, it may be a plug-in hard disk, a Smart Media Card (SMC), a Secure Digital (SD) card, a Flash Card, etc. equipped on the terminal device. The memory may also include both the internal storage unit and the external storage device of the terminal device. The memory is used to store an operating system, application programs, a Boot Loader, data, and other programs, such as program codes of computer programs. The memory may also be used to temporarily store data that has been output or is to be output.

[0158] In an application, the communication module may be set as any device capable of directly or indirectly performing long-distance wired or wireless communication with a user terminal according to actual needs. For example, the communication module may provide communication solutions applied on network devices, including Wireless Local Area Networks (WLANs) (such as Wi-Fi networks), Bluetooth, Zigbee, mobile communication networks, Global Navigation Satellite System (GNSS), Frequency Modulation (FM), Near Field Communication (NFC), Infrared (IR), etc. The communication module may include an antenna. The antenna may have only one element or may be an antenna array including multiple elements. The communication module may receive electromagnetic waves through the antenna, perform frequency modulation and filtering processing on the electromagnetic wave signals, and send the processed signals to the processor. The communication module may also receive signals to be sent from the processor, perform frequency modulation and amplification on them, and convert them into electromagnetic waves through the antenna for radiation.

[0159] It should be noted that for the content such as information interaction and execution process between the above-mentioned devices / modules, since it is based on the same concept as the method embodiment of the present application, for its specific functions and the technical effects brought, reference may be specifically made to the method embodiment part, and details are not described herein again.

[0160] Those skilled in the art can clearly understand that, for the convenience and simplicity of description, only the above division of each functional module is used as an example. In actual applications, the above functions can be allocated to different functional modules as needed, that is, the internal structure of the device is divided into different functional modules to complete all or part of the functions described above. Each functional module in the embodiment can be integrated into a processing module, or each module can exist physically alone, or two or more modules can be integrated into one module. The above integrated module can be implemented in the form of hardware or in the form of a software functional module. In addition, the specific names of each functional module are only for the convenience of mutual distinction and do not limit the protection scope of this application. The specific working process of the modules in the above system can refer to the corresponding process in the foregoing method embodiment and will not be elaborated here.

[0161] The embodiment of the present application also provides a computer-readable storage medium. A computer program is stored in the computer-readable storage medium, and when the computer program is executed by a processor, the steps in the foregoing method embodiments can be implemented.

[0162] The embodiment of the present application provides a computer program product. When the computer program product runs on a terminal device, the terminal device can implement the steps in the foregoing method embodiments.

[0163] If the above integrated module is implemented in the form of a software functional module and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, to implement all or part of the processes in the above method embodiments of the present application, a computer program can be used to instruct relevant hardware to complete. The computer program can be stored in a computer-readable storage medium. When the computer program is executed by a processor, the steps in the foregoing method embodiments can be implemented. Among them, the computer program includes computer program code, and the computer program code can be in the form of source code, object code, executable file or some intermediate form, etc. The computer-readable medium can at least include: any entity or device that can carry the computer program code to the terminal device, recording medium, computer memory, read-only memory (ROM), random access memory (RAM), electrical carrier signal, telecommunication signal, and software distribution medium. For example, a USB flash drive, a mobile hard disk, a magnetic disk or an optical disc, etc.

[0164] In the above embodiments, the descriptions of each embodiment have their own emphases. For the parts not detailed or recorded in a certain embodiment, reference can be made to the relevant descriptions of other embodiments.

[0165] Those of ordinary skill in the art can realize that the modules and algorithm steps of each example described in combination with the embodiments disclosed herein can be implemented by electronic hardware, or a combination of computer software and electronic hardware. Whether these functions are executed in a hardware or software manner depends on the specific application and design constraints of the technical solution. A professional technician can use different methods for each specific application to implement the described functions, but such implementation should not be considered to exceed the scope of this application.

[0166] In the embodiments provided in this application, it should be understood that the disclosed devices and methods can be implemented in other ways. For example, the device embodiments described above are merely illustrative. For example, the division of the modules is only a logical function division. In actual implementation, there may be other division methods. For example, multiple modules or components can be combined or integrated into another system, or some features can be ignored or not executed. Another point is that the displayed or discussed couplings or direct couplings or communication connections to each other can be through some interfaces. The indirect couplings or communication connections of devices or modules can be in electrical, mechanical or other forms.

[0167] The modules described as separate components may or may not be physically separated. The components displayed as modules may or may not be physical modules, that is, they can be located in one place, or they can be distributed to multiple network modules. Some or all of the modules can be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0168] The above-described embodiments are only used to illustrate the technical solutions of this application, rather than to limit them. Although this application has been described in detail with reference to the foregoing embodiments, those of ordinary skill in the art should understand that they can still modify the technical solutions recorded in the foregoing embodiments, or perform equivalent replacements on some of the technical features. And these modifications or replacements do not make the essence of the corresponding technical solutions deviate from the spirit and scope of the technical solutions of the embodiments of this application, and should all be included in the protection scope of this application.

Claims

1. A radiation monitoring method, characterized in that: Applied to a reactor pressure vessel, the method comprises: Determine the target unit based on the judgment conditions of multi-unit linkage irradiation supervision; Formulate an irradiation monitoring plan for the target unit; According to the irradiation supervision plan, the irradiation supervision data of the target unit is obtained and output.

2. The irradiation monitoring method according to claim 1, characterized in that: The step of determining the target unit according to the judgment conditions of the multi-unit linkage irradiation supervision comprises: Establish the judgment conditions for multi-unit linkage irradiation supervision; The information of the target nuclear power plant is obtained, and a nuclear power unit in the target nuclear power plant that meets the determination condition is determined as the target unit.

3. The irradiation monitoring method according to claim 2, characterized in that: The determination conditions for establishing multi-unit linkage irradiation supervision include: Establish any one or more of the first judgment condition based on the reactor structure design parameters, the second judgment condition based on the core and fuel management mode parameters, and the third judgment condition based on the material parameters of the reactor pressure vessel.

4. The irradiation monitoring method according to claim 3, characterized in that: The reactor structural design parameters include multiple ones of the inner diameter of the core barrel, the water gap, the height of the active section, the design pressure, the design temperature, the operating pressure, the overall height of the reactor pressure vessel, the reactor pressure vessel outlet temperature, the reactor pressure vessel inlet temperature and the materials of the reactor internal components; The core and fuel management mode parameters include multiple ones of core rated power, core thermal power, core layout shape, fuel assembly model, fuel assembly quantity, refueling cycle, control rod quantity and control rod layout; The material parameters of the reactor pressure vessel include multiple ones of the chemical composition, initial mechanical properties and radiation embrittlement model of the material of the reactor pressure vessel.

5. The irradiation monitoring method according to any one of claims 1 to 4, characterized in that: The step of formulating the irradiation monitoring plan for the target unit includes: In the target unit, determining a preset number of irradiation supervision samples; Establish an irradiation supervision cycle.

6. The irradiation monitoring method according to claim 5, characterized in that: The step of obtaining and outputting the irradiation monitoring data of the target unit according to the irradiation monitoring plan includes: Extracting a plurality of target irradiation supervision samples that meet the irradiation supervision cycle from the preset number of irradiation supervision samples; The plurality of target irradiation monitoring samples are tested, and the irradiation monitoring data of the plurality of target irradiation monitoring samples are obtained and output.

7. The irradiation monitoring method according to claim 5, characterized in that: The irradiation monitoring cycle is formulated, including: Establishing a plurality of said irradiation monitoring cycles; Accordingly, obtaining and outputting the irradiation supervision data of the target unit according to the irradiation supervision plan includes: Extracting a plurality of target irradiation supervision samples satisfying each irradiation supervision cycle from the preset number of irradiation supervision samples; The plurality of target irradiation supervision samples of the plurality of irradiation supervision cycles are tested, and the irradiation supervision data of the plurality of target irradiation supervision samples are obtained and output.

8. An irradiation monitoring device, characterized in that: Applied to a reactor pressure vessel, the device comprises: A target determination module is used to determine the target unit according to the judgment conditions of multi-unit linkage irradiation supervision; A plan making module, for making an irradiation monitoring plan for the target unit; The data acquisition module is used to acquire and output the irradiation monitoring data of the target unit according to the irradiation monitoring plan.

9. A terminal device, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that: When the processor executes the computer program, the steps of the irradiation supervision method according to any one of claims 1 to 7 are implemented.

10. A computer program product, characterized in that The computer program product comprises a computer program, and when the computer program is executed by a processor, the steps of the irradiation supervision method according to any one of claims 1 to 7 are implemented.

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