Method and device for starting up a first cycle of a nuclear reactor, electronic device and storage medium

Abstract

The application provides a nuclear reactor first cycle starting method and device, an electronic device and a storage medium, and belongs to the technical field of nuclear power. The application obtains neutron intensity change data of a secondary neutron source assembly, the neutron intensity change data including time steps and neutron release intensity of the time steps, selects the smallest neutron release intensity from the neutron intensity change data as a target neutron intensity, obtains the time step of the target neutron intensity if the target neutron intensity is greater than or equal to a preset neutron intensity threshold, obtains a target time, determines a target reactor entry time period of the secondary neutron source assembly according to the target time and a pre-obtained reactor starting time of the target nuclear reactor, and performs first cycle starting on the target nuclear reactor according to the target reactor entry time period and the secondary neutron source assembly. The application can allocate appropriate reactor entry time for the secondary neutron source assembly, and realizes first cycle starting of the nuclear reactor using the secondary source assembly to replace the primary source.

Description

Technical Field

[0001] The present application relates to the field of nuclear power technology, and in particular to a method and device for starting a nuclear reactor for the first cycle, an electronic device, and a storage medium. Background Art

[0002] In the related art, the 252 A primary neutron source assembly made of Cf material provides neutrons for the first startup cycle of a nuclear reactor. Because primary neutron source assemblies are difficult to obtain, irradiated secondary neutron source assemblies from existing nuclear power units are typically used as neutron providers for the first startup cycle of a nuclear reactor. When using a secondary neutron source assembly as a neutron provider, the time for its placement in the reactor must be planned in advance. If the planned placement time is inappropriate, the secondary neutron source assembly's source intensity will not meet the required level, preventing the reactor from achieving criticality or causing a loss of core monitoring during startup, impacting the reactor's first startup cycle. Summary of the Invention

[0003] The main purpose of the embodiments of the present application is to propose a method and device for the first cycle startup of a nuclear reactor, an electronic device and a storage medium, aiming to determine a suitable time for the secondary neutron source assembly to enter the reactor and realize the first cycle startup of the nuclear reactor.

[0004] To achieve the above-mentioned objectives, a first aspect of an embodiment of the present application provides a method for starting a nuclear reactor for the first cycle, the method comprising:

[0005] Acquiring neutron intensity variation data of a secondary neutron source assembly; wherein the secondary neutron source assembly is an irradiated neutron source assembly, the neutron intensity variation data includes a time step and a neutron release intensity in the time step, and the neutron intensity variation data is used to characterize a variation trend of the neutron release intensity with the time step;

[0006] Selecting the minimum neutron release intensity from the neutron intensity variation data as the target neutron intensity;

[0007] If the target neutron intensity is greater than or equal to a preset neutron intensity threshold, obtaining the time step of the target neutron intensity to obtain a target time;

[0008] determining a target reactor loading time period for the secondary neutron source assembly based on the target time and a pre-acquired startup duration of the target nuclear reactor;

[0009] The target nuclear reactor is started up for the first time according to the target loading time period and the secondary neutron source assembly.

[0010] In some embodiments, the secondary neutron source assembly includes a target nuclide, and obtaining neutron intensity variation data of the secondary neutron source assembly includes:

[0011] Get the time step;

[0012] Acquire the number of nuclides of the target nuclide according to the time step to obtain the target nuclide number;

[0013] converting the target nuclide quantity into neutron release intensity;

[0014] The neutron intensity variation data is obtained according to the time step and the neutron release intensity in the time step.

[0015] In some embodiments, acquiring the target nuclide quantity according to the time step to obtain the target nuclide quantity includes:

[0016] Acquire the irradiated neutron flux of the target nuclear reactor according to the time step;

[0017] The target nuclide quantity is obtained by performing nuclide quantity statistics on the time step, the irradiation neutron flux, the pre-acquired decay coefficient of the secondary neutron source component, and the pre-acquired nuclear reaction cross section of the secondary neutron source component through a preset nuclide quantity statistical model.

[0018] In some embodiments, the secondary neutron source assembly further includes a first nuclide and a second nuclide, the target nuclide is generated by a nuclear reaction between the first nuclide and the second nuclide, and the preset nuclide quantity statistical model is constructed according to the following steps:

[0019] Obtaining the nuclide quantity of the first nuclide to obtain an initial nuclide quantity;

[0020] performing a model analysis on a first preset nuclide quantity change rate model based on the initial nuclide quantity to obtain a first nuclide quantity statistical model; the first preset nuclide quantity change rate model is used to characterize the nuclide quantity change rate of the first nuclide; the first nuclide quantity statistical model is used to count the nuclide quantity of the first nuclide;

[0021] updating a second preset nuclide quantity change rate model according to the first nuclide quantity statistical model to obtain a third preset nuclide quantity change rate model; the second preset nuclide quantity change rate model is used to characterize the nuclide quantity change rate of the target nuclide;

[0022] The third preset nuclide quantity change rate model is integrated in the time dimension to obtain the preset nuclide quantity statistical model.

[0023] In some embodiments, before determining the target loading time period of the secondary neutron source assembly based on the target time and the pre-acquired startup duration of the target nuclear reactor, the nuclear reactor first cycle startup method further includes:

[0024] Obtaining the startup duration includes:

[0025] Acquiring a first time when a nuclear power unit including the target nuclear reactor is in a first state;

[0026] Obtaining the current unit power of the nuclear power unit;

[0027] If the current unit power is greater than or equal to a preset power threshold, switching the nuclear power unit from the first state to a second state, and obtaining a second time for the nuclear power unit to switch from the first state to the second state;

[0028] The startup duration is determined according to the first time and the second time.

[0029] In some embodiments, determining the target loading period of the secondary neutron source assembly according to the target time and a pre-acquired startup duration of the target nuclear reactor includes:

[0030] Determining a target reactor loading time for the secondary neutron source assembly based on the target time and a pre-acquired startup duration of the target reactor;

[0031] Obtaining the time when the secondary neutron source assembly is removed from the initial nuclear reactor to obtain the initial reactor entry time;

[0032] The target stacking time period is determined according to the initial stacking time and the target stacking time.

[0033] In some embodiments, determining the target stacking time period according to the initial stacking time and the target stacking time includes:

[0034] Constructing a time interval according to the initial loading time and the target loading time to obtain an initial loading time period;

[0035] Obtaining a component reference period of the secondary neutron source component; wherein the component reference period is an unavailable period;

[0036] Performing a first period adjustment on the initial stacking period according to the component reference period to obtain a reference stacking period;

[0037] The reference reactor loading period is adjusted for a second period according to the reactor loading period condition of the target nuclear reactor to obtain the target reactor loading period.

[0038] To achieve the above-mentioned objectives, a second aspect of an embodiment of the present application provides a nuclear reactor first cycle startup device, the device comprising:

[0039] a first acquisition module, configured to acquire neutron intensity variation data of a secondary neutron source assembly; wherein the secondary neutron source assembly is an irradiated neutron source assembly, the neutron intensity variation data including a time step and a neutron release intensity at the time step, the neutron intensity variation data being used to characterize a variation trend of the neutron release intensity with respect to the time step;

[0040] a screening module, configured to select the minimum neutron release intensity from the neutron intensity variation data as a target neutron intensity;

[0041] A second acquisition module is configured to acquire the time step of the target neutron intensity to obtain a target time if the target neutron intensity is greater than or equal to a preset neutron intensity threshold;

[0042] A determination module, configured to determine a target loading time period of the secondary neutron source assembly according to the target time and a pre-acquired startup duration of the target nuclear reactor;

[0043] A startup module is used to perform an initial cycle startup of the target nuclear reactor according to the target loading time period and the secondary neutron source assembly.

[0044] To achieve the above-mentioned purpose, the third aspect of an embodiment of the present application proposes an electronic device, which includes a memory and a processor. The memory stores a computer program, and when the processor executes the computer program, it implements the nuclear reactor first cycle startup method of the above-mentioned first aspect.

[0045] To achieve the above-mentioned purpose, the fourth aspect of the embodiment of the present application proposes a computer-readable storage medium, which stores a computer program. When the computer program is executed by a processor, it implements the nuclear reactor first cycle startup method of the above-mentioned first aspect.

[0046] The present application proposes a method, device, electronic device, and computer-readable storage medium for the initial startup of a nuclear reactor. By acquiring neutron intensity variation data from a secondary neutron source assembly, the neutron release intensity at each time step is determined based on the neutron intensity variation data. When the nuclear reactor is initially started and in a low-power phase, the neutron release intensity is minimal. Therefore, the minimum neutron release intensity from the neutron intensity variation data is selected as the target neutron intensity. A target neutron intensity that is too low cannot provide sufficient neutrons for the nuclear reactor, posing a risk of losing core monitoring. The target neutron intensity is then compared with a preset neutron intensity threshold to determine whether it meets the intensity requirements. If the target neutron intensity is greater than or equal to the preset neutron intensity threshold, it indicates that the target neutron intensity meets the intensity requirements and that the secondary neutron source assembly can serve as the neutron source for the initial startup of the nuclear reactor. The time step of the target neutron intensity is then acquired to obtain the target time. A nuclear reactor requires a certain amount of time for loading and starting. Based on the target time and the pre-acquired start-up time of the target nuclear reactor, the target loading period of the secondary neutron source assembly is determined, so that the secondary neutron source assembly can be loaded into the nuclear reactor during the target loading period, realizing the first cycle startup of the nuclear reactor using the secondary source assembly instead of the primary source. BRIEF DESCRIPTION OF THE DRAWINGS

[0047] Figure 1 This is a flow chart of a method for starting a nuclear reactor for the first cycle provided in an embodiment of the present application;

[0048] Figure 2 yes Figure 1 Flowchart of step S120 in FIG.

[0049] Figure 3 yes Figure 2 Flowchart of step S210 in FIG.

[0050] Figure 4 yes Figure 3 Flowchart of step S330 in FIG.

[0051] Figure 5 yes Figure 4 Flowchart of step S410 in FIG.

[0052] Figure 6 yes Figure 1 Flowchart of step S140 in FIG.

[0053] Figure 7 is another flow chart of the method for starting up a nuclear reactor for the first cycle provided in an embodiment of the present application;

[0054] Figure 8 1 is a schematic structural diagram of a nuclear reactor first cycle startup device provided in an embodiment of the present application;

[0055] Figure 9 This is a schematic diagram of the hardware structure of the electronic device provided in an embodiment of the present application. DETAILED DESCRIPTION

[0056] In order to make the purpose, technical solutions and advantages of this application more clear, the following further describes this application in detail with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain this application and are not intended to limit this application.

[0057] It should be noted that although the device schematics illustrate functional module divisions and the flowcharts illustrate logical sequences, in certain circumstances, the steps shown or described may be performed in a sequence that differs from the module divisions in the device or the sequence in the flowcharts. The terms "first," "second," and so on, in the specification, claims, and drawings, are used to distinguish similar items and are not necessarily used to describe a specific sequence or precedence.

[0058] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by those skilled in the art to which this application pertains. The terms used herein are for the purpose of describing the embodiments of this application only and are not intended to limit this application.

[0059] In the related art, the 252 A primary neutron source assembly made of Cf material provides neutrons for the first startup cycle of a nuclear reactor. Due to the uncertainty surrounding the availability of primary neutron source assemblies, irradiated secondary neutron source assemblies from existing nuclear power units are used as alternative neutron providers for the first startup cycle of a nuclear reactor. When using secondary neutron source assemblies as neutron providers, the time for their placement in the reactor must be planned in advance. If the planned placement time is inappropriate, the secondary neutron source assembly's source intensity will not meet the required level, preventing the reactor from achieving criticality or causing instability during startup, impacting the reactor's first startup cycle.

[0060] Based on this, the embodiments of the present application provide a nuclear reactor first cycle startup method, a nuclear reactor first cycle startup device, an electronic device and a computer-readable storage medium, aiming to realize the first cycle startup of a nuclear reactor using a secondary source component instead of a primary source.

[0061] The nuclear reactor first cycle startup method, nuclear reactor first cycle startup device, electronic device and computer-readable storage medium provided in the embodiments of the present application are specifically illustrated through the following embodiments. First, the nuclear reactor first cycle startup method in the embodiments of the present application is described.

[0062] The method for starting a nuclear reactor for the first cycle provided in the embodiment of the present application relates to the field of nuclear power technology. The method for starting a nuclear reactor for the first cycle provided in the embodiment of the present application can be applied to a terminal, can be applied to a server side, or can be software running in a terminal or a server side. In some embodiments, the terminal can be a smart phone, a tablet computer, a laptop computer, a desktop computer, etc.; the server side can be configured as an independent physical server, or as a server cluster or distributed system composed of multiple physical servers, or as a cloud server that provides basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communications, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application that implements the method for starting a nuclear reactor for the first cycle, etc., but is not limited to the above forms.

[0063] The present application can be used in many general or special computer system environments or configurations. For example: personal computers, server computers, handheld or portable devices, tablet devices, multiprocessor systems, microprocessor-based systems, set-top boxes, programmable consumer electronics, network PCs, minicomputers, mainframe computers, distributed computing environments including any of the above systems or devices, and the like. The present application can be described in the general context of computer-executable instructions executed by a computer, such as program modules. Generally, program modules include routines, programs, objects, components, data structures, and the like that perform specific tasks or implement specific abstract data types. The present application can also be practiced in distributed computing environments in which tasks are performed by remote processing devices connected via a communication network. In a distributed computing environment, program modules can be located in local and remote computer storage media, including storage devices.

[0064] Figure 1 This is an optional flow chart of a method for starting a nuclear reactor for the first cycle provided in an embodiment of the present application. Figure 1 The method may include but is not limited to steps S110 to S150.

[0065] Step S110, obtaining neutron intensity variation data of a secondary neutron source assembly; wherein the secondary neutron source assembly is an irradiated neutron source assembly, and the neutron intensity variation data includes a time step and a neutron release intensity in the time step, and the neutron intensity variation data is used to characterize a variation trend of the neutron release intensity over the time step;

[0066] Step S120, selecting the minimum neutron release intensity from the neutron intensity variation data as the target neutron intensity;

[0067] Step S130, if the target neutron intensity is greater than or equal to the preset neutron intensity threshold, obtaining a time step of the target neutron intensity to obtain a target time;

[0068] Step S140, determining a target time period of the secondary neutron source assembly into the target nuclear reactor according to the target time and the pre-acquired start-up time length of the target nuclear reactor;

[0069] Step S150, performing first cycle start-up of the target nuclear reactor by the secondary neutron source assembly according to the target time period of the secondary neutron source assembly into the target nuclear reactor.

[0070] The secondary neutron source assembly is an important component of the nuclear reactor core, and is used to provide sufficient neutron fluence level for the nuclear reactor. The secondary neutron source assembly is composed of antimony-beryllium (Sb-Be) pellets wrapped in a stainless steel cladding. The secondary neutron source assembly includes a first nuclide and a second nuclide, the first nuclide is antimony (Sb), and the first nuclide adopts 123 Sb, and the second nuclide is beryllium (Be), and the second nuclide adopts 9 Be. The secondary neutron source assembly further includes a target nuclide, the target nuclide is 124 Sb, and the target nuclide is generated by a nuclear reaction between the first nuclide and the second nuclide. High-energy gamma rays and the second nuclide undergo (gamma, neutron) photo-nuclear reactions to generate neutrons, and the first nuclide undergoes (n, gamma) activation reactions under neutron irradiation to proliferate into the target nuclide. Since there are uncertain factors in obtaining the primary neutron source assembly, the secondary neutron source assembly is used to replace the initial nuclear reactor for baking, and the baked secondary neutron source assembly is removed from the initial nuclear reactor and loaded into the target nuclear reactor, and the neutrons generated by the secondary neutron source assembly are used to complete the first cycle start-up of the target nuclear reactor. The initial nuclear reactor is a nuclear reactor that has completed the first cycle start-up and is in stable operation, and the target nuclear reactor is a nuclear reactor to be started up for the first cycle. The first cycle start-up of the nuclear reactor refers to the first use of the nuclear reactor. After removing the secondary neutron source assembly from the initial nuclear reactor, the target nuclide will decay at a half-life of about 60 days and release gamma rays, and the photo-nuclear reaction of the generated gamma rays with the second nuclide releases neutrons. The source strength of the secondary neutron source assembly is related to the gamma rays released by the target nuclide and the number of target nuclides.

[0071] Please refer to Figure 2 In some embodiments, step S110 can include but is not limited to steps S210 to S240:

[0072] Step S210, obtaining a time step;

[0073] Step S220, obtaining a nuclide number of the target nuclide according to the time step to obtain a target nuclide number;

[0074] Step S230, converting the target nuclide quantity into neutron release intensity;

[0075] Step S240 , obtaining neutron intensity variation data according to the time step and the neutron release intensity of the time step.

[0076] In step S210 of some embodiments, whether the target nuclear reactor can successfully complete the first cycle startup is related to the source strength of the secondary neutron source assembly. When the source strength reaches the required source strength condition, the target nuclear reactor can successfully complete the first cycle startup. For the first reactor of a nuclear power plant, such as the first reactor of a model or the first reactor of a site, there is a large uncertainty in the loading and startup period. Equipment problems, installation constraints, and even disturbances such as unexpected reactor jumps of the unit after startup will all affect the availability of the secondary neutron source assembly. In addition, the firing of the secondary neutron source assembly needs to be carried out within the existing operating unit (12-18 month cycle), and most of the matching analysis and decision-making of the secondary neutron source assembly need to be carried out 20-30 months before loading, which further increases the risk of secondary neutron source assembly availability decision-making. This application obtains neutron intensity variation data by analyzing the proliferation and decay processes of target nuclides in secondary neutron source assemblies, and determines the appropriate reactor entry time window in advance based on the neutron intensity variation data, so that the reactor entry time window matches the loading time window of the target reactor, thereby ensuring the availability of the secondary source neutron assembly and reducing the risk of availability decision-making.

[0077] The prediction of the reactor entry time window is not based solely on a single point in time; it also requires comprehensive consideration from multiple perspectives, including project duration risk and decay characteristics. By accounting for the decay characteristics of the target nuclides and the uncertainty of the loading and startup periods, the accuracy of the prediction of the reactor entry time window can be improved. A time step is a time point within a preset period, used to measure the time after the secondary neutron source assembly is removed from the reactor. The preset period includes the period after the secondary neutron source assembly is removed from the initial nuclear reactor and the preset risk period. The preset risk period is the pre-set risk period for each stage of the target nuclear reactor, from loading to startup. The target nuclear reactor's loading to startup phase primarily includes loading, pre-criticality, startup, and power ramp-up. The preset risk periods are shown in Table 1.

[0078] Table 1

[0079]

[0080] Due to unplanned reactor trips caused by equipment or design issues during the startup and power ramp-up phases, Table 2 assumes a construction period with 10 unplanned reactor trips and 5 unplanned outages, where FP represents full power. As a conservative limit for analyzing the actual decay of the secondary neutron source components in the first reactor, as long as the first reactor construction period does not exceed this assumed period, the residual activity of the secondary neutron source components will still meet the unit restart requirements.

[0081] Table 2

[0082]

[0083] In step S220 of some embodiments, the number of target nuclides at each time step in a preset period is obtained, to obtain the number of target nuclides at each time step.

[0084] In step S230 of some embodiments, the neutron release intensity is the source intensity of the secondary neutron source assembly. Since the neutron release intensity is related to the number of target nuclides, the number of target nuclides can be used as the neutron release intensity, and the number of target nuclides is used to represent the neutron release intensity.

[0085] In step S240 of some embodiments, the time step and the neutron release intensity at the time step are taken as the neutron intensity change data. Alternatively, the time step is taken as the horizontal axis, and the neutron release intensity at the time step is taken as the vertical axis. The time step and the neutron release intensity are plotted by a plotting tool to obtain the neutron intensity change data of the irradiated secondary neutron source assembly. Alternatively, the neutron release intensity at each time step is sequentially arranged according to the time step sequence, and the arranged time step and the neutron release intensity are taken as the neutron intensity change data. The neutron intensity change data is used to represent the change of the neutron release intensity with the time step. The irradiated secondary neutron source assembly is a secondary source assembly that has been fired by an existing nuclear power unit.

[0086] Through the above steps S210 to S240, the neutron intensity change data can be obtained, and the appropriate time of the secondary neutron source assembly into the reactor can be determined based on the neutron intensity change data.

[0087] Referring to Figure 3 In some embodiments, step S220 can include but is not limited to steps S310 to S320:

[0088] In step S310, the irradiation neutron flux of the target nuclear reactor is obtained according to the time step.

[0089] In step S320, the number of target nuclides is counted by a preset nuclide number counting model according to the time step, the irradiation neutron flux, the pre-obtained decay coefficient of the secondary neutron source assembly, and the pre-obtained nuclear reaction cross section of the secondary neutron source assembly, to obtain the number of target nuclides.

[0090] In step S310 of some embodiments, in combination with the core design parameters of the target nuclear reactor core such as uranium enrichment, assembly size, reflector and core size, etc., the neutron release intensity at the position of the external nuclear instrument of the target nuclear reactor pressure vessel can be obtained by simulating the multiplication and decay of the target nuclide through the Monte Carlo simulation technology within the preset risk period. Assuming that the secondary neutron source assembly has been loaded into the target nuclear reactor, the first nuclide in the secondary neutron source assembly is converted into the target nuclide under neutron irradiation in the core, at this time the target nuclide has both multiplication effect and decay effect, and the number of the target nuclide is related to the multiplication rate and the decay rate. It should be noted that, 124 Sb itself will continue to decay, and only in a neutron environment above a certain intensity can sufficient activation reaction be generated, 124 Sb can obtain effective multiplication. The in-service nuclear power unit can provide such an environment for the secondary neutron source assembly, and the operation cycle of the in-service nuclear power unit is generally 12-18 months, so the secondary neutron source assembly can effectively multiply in this period of time to form a secondary neutron source assembly with a certain neutron release intensity. However, 124 Sb is not infinite multiplication, when 124 Sb accumulates to a certain amount, 124 Sb the decay rate gradually and 124 Sb the multiplication rate reaches balance, and the multiplication of the secondary neutron source assembly reaches saturation.

[0091] After the first loading, the target nuclear reactor is in a subcritical or low-power state, and there is no neutron environment in the reactor that can effectively multiply 124 Sb, and the source intensity of the secondary neutron source assembly (secondary source) will still decrease over time. Therefore, for the matching analysis of the source intensity of the secondary source, the power change of the nuclear power unit after loading should be fully considered. Whether the target nuclide in the secondary source multiplies or not is related to the power of the nuclear power unit to which the target nuclear reactor belongs. When the power of the nuclear power unit to which the target nuclear reactor belongs reaches a certain power level, the secondary source will multiply. The power level is generally about 2% of the full power of the nuclear power plant. The irradiation neutron flux is used to represent the neutron flux level of the environment in which the secondary neutron source assembly is located, and the irradiation neutron flux is related to the power of the nuclear power unit to which the target nuclear reactor belongs. The irradiation neutron flux is represented as φ = P·φ FP , where φ FP represents the neutron flux level under full power, P represents the power of the nuclear power unit, 0 ≤ P ≤ 100%, and φ represents the irradiation neutron flux. It should be noted that when the secondary neutron source assembly is removed from the initial nuclear reactor, P is 0, and the secondary neutron source assembly is not in a multiplication state, 124Sb only has a decay effect. Therefore, when the time step is in the period after the secondary neutron source assembly is removed from the initial nuclear reactor, the irradiation neutron flux of this time step is 0. When the time step is in the preset risk period, the irradiation neutron flux of this time step is related to the power of the nuclear power unit.

[0092] In step S320 of some embodiments, the decay coefficient is a parameter describing the decay rate of the target nuclide, which is a dimensionless constant with a unit of seconds (s). -1 ). 124 The decay coefficient of Sb can be 1.33×10 -7 s -1 The nuclear reaction cross section is a physical quantity that describes the probability of a nuclear reaction. It is used to measure the probability of a specific reaction between an incident particle and a target nucleus. The time step, irradiation neutron flux, decay coefficient of the secondary neutron source component, and nuclear reaction cross section are input into the preset nuclide population statistical model to perform nuclide population statistics and obtain the target nuclide population for that time step. The preset nuclide population statistical model is used to count the target nuclide population at each time step.

[0093] Through the above steps S310 to S320, the number of target nuclides in each time step can be obtained. The changing trend of the target nuclides in multiple time steps can reflect the changing trend of the source strength, so that a suitable loading time window can be selected based on the changing trend to ensure the availability of the secondary source.

[0094] See also Figure 4 In some embodiments, the process of constructing the preset nuclide quantity statistical model may include but is not limited to steps S410 to S440:

[0095] Step S410, obtaining the nuclide quantity of the first nuclide to obtain the initial nuclide quantity;

[0096] Step S420: performing a model analysis on the first preset nuclide quantity change rate model based on the initial nuclide quantity to obtain a first nuclide quantity statistical model; the first preset nuclide quantity change rate model is used to characterize the nuclide quantity change rate of the first nuclide; the first nuclide quantity statistical model is used to calculate the nuclide quantity of the first nuclide;

[0097] Step S430: updating the second preset nuclide quantity change rate model according to the first nuclide quantity statistical model to obtain a third preset nuclide quantity change rate model; the second preset nuclide quantity change rate model is used to characterize the nuclide quantity change rate of the target nuclide;

[0098] Step S440: performing model integration on the third preset nuclide quantity change rate model in the time dimension to obtain a preset nuclide quantity statistical model.

[0099] In step S410 of some embodiments, the number of the first nuclide in the secondary neutron source component under the initial condition is obtained to obtain the initial nuclide number. The initial nuclide number is the number of the first nuclide in the secondary neutron source component under the initial condition. 123 The atomic number (number of nuclides) of Sb. The initial condition refers to the secondary neutron source component not being activated by neutron irradiation, that is, the secondary neutron source component is not fired.

[0100] In step S420 of some embodiments, the first preset nuclide quantity change rate model is used to characterize the first nuclide 123 The rate of change of the number of nuclides of Sb is the rate of change of the number of nuclides of the first nuclide over time. The first preset rate of change of the number of nuclides is expressed as:

[0101]

[0102] in, is the rate of change of the number of nuclides of the first nuclide; N a (t) is the time step t 123 The atomic number of Sb; σ represents 123 Sb reacts with neutrons to produce 124 The nuclear reaction cross section of Sb; φ represents the irradiation neutron flux.

[0103] Formula (1) is a first-order linear differential equation, and the initial number of nuclides is the time step 0. 123 The number of Sb atoms is calculated by solving the first preset nuclide quantity change rate model based on the initial nuclide quantity to obtain a first nuclide quantity statistical model. The first nuclide quantity statistical model is used to count the nuclide quantity of the first nuclide at each time step. The first nuclide quantity statistical model is the integral of the first preset nuclide quantity change rate model in the time dimension. The first nuclide quantity statistical model is expressed as:

[0104] N a (t) = Noe -σφt , formula (2)

[0105] Where N0 is the initial number of nuclides.

[0106] In step S430 of some embodiments, the second preset nuclide quantity change rate model is used to characterize the target nuclide 124 The nuclide quantity change rate of Sb is the speed at which the target nuclide quantity changes over time. The second preset nuclide quantity change rate model is expressed as:

[0107]

[0108] in, is the target nuclide number change rate; P is the target nuclide production rate; D is the target nuclide decay rate; N a (t) is the time step t123 The atomic number of Sb; σ represents 123 Sb reacts with neutrons to produce 124 The nuclear reaction cross section of Sb; φ represents the irradiation neutron flux; λ is the decay coefficient; N(t) is the time step t 124 The atomic number of Sb.

[0109] Substitute the first nuclide quantity statistical model into the second preset nuclide quantity change rate model, update the second preset nuclide quantity change rate model, and obtain a third preset nuclide quantity change rate model. The third preset nuclide quantity change rate model is used to characterize the target nuclide. 124 The rate of change of the number of nuclides of Sb is expressed as:

[0110]

[0111] In step S440 of some embodiments, the third preset nuclide population change rate model is a first-order linear non-homogeneous differential equation, and the third preset nuclide population change rate model can be solved using the constant variation method. Specifically, the third preset nuclide population change rate model is integrated over the time dimension to obtain a preset nuclide population statistical model. Since no activation reaction occurs under initial conditions, the nuclide population of the target nuclide is 0, that is, N(t) is 0, where t is 0. Solving the preset nuclide population statistical model based on N(t) = 0 yields:

[0112]

[0113] Neutron intensity variation data includes the initial time step and the initial source strength. The initial time step is the first time step in the chronological order and is the starting point of the preset time period. The initial time step is 0, indicating that the secondary neutron source assembly has just been fired out of the reactor. The initial source strength is the neutron release intensity in the first time step, that is, the neutron release intensity after the secondary neutron source assembly is fired out of the reactor. The initial source strength, i.e., the number of target nuclides, can be determined by using formula (5) and the firing time of the secondary neutron source assembly in the operating unit.

[0114] In the above steps S410 to S440, a preset nuclide quantity statistical model is constructed by using the change rate of the first nuclide and the change rate of the target nuclide, so as to obtain the nuclide quantity of the target nuclide that changes with time using the preset nuclide quantity statistical model.

[0115] In step S120 of some embodiments, the source range meter quantity of the initial time step is determined by combining the initial source strength and the nuclear instrument detector arranged outside the target nuclear reactor core. The source range meter quantity is the product of the source strength at the position of the source range probe and the sensitivity of the nuclear instrument detector, and its unit is cps. The source range meter quantity A(0) of the initial time step of a certain nuclear power plant can be 130 cps. It should be noted that after the nuclear reactor core structure and the loading arrangement are fixed, the relationship (sensitivity) between the secondary source source strength and the source range meter quantity is a fixed coefficient. After the secondary neutron source assembly is separated from the breeding environment of the initial nuclear reactor, the burning time of the secondary neutron source assembly in the initial nuclear reactor can be substituted into formula (2) and formula (5), the nuclide quantity Na1 of the first nuclide at the initial time step (after the reactor) is obtained through formula (2), and the target nuclide quantity N1 of the target nuclide at the initial time step is obtained through formula (5). According to Na1 and N and combining the irradiation neutron flux φ after the reactor, the target nuclide quantity changes with time, and the subsequent secondary source source strength changes with time can be obtained. In order to simplify the analysis, the source strength change can be integrated and calculated in units of unit power instead of irradiation neutron flux. According to the relationship between the secondary source source strength and the source range meter quantity, the neutron intensity change data can be converted into nuclear instrument count change data that can be monitored. The nuclear instrument count change data includes time steps and source range meter quantities of neutron release intensity at the time steps, and the nuclear instrument count change data can be described in a curve manner.

[0116] In the related art, the target node is usually the loading, and the availability of the secondary source assembly at the first loading is taken as the evaluation index. However, after the first loading, the reactor core of the unit is still in a subcritical state or a low-power state, and the secondary source strength still decays according to the half-life of about 60 days. If the secondary source strength is too low at this time or faces major constraints of unit design and equipment, the secondary source strength may not meet the minimum source strength requirement of the unit startup. In order to ensure the availability of the secondary neutron source assembly, the effect of the nuclear power unit power on the source strength needs to be considered. It should be noted that the continuous decay of the secondary neutron source assembly makes it have a maximum available duration after being taken out of the reactor. When the secondary neutron source assembly is used to start the nuclear power unit, the unit startup and power increase should be completed within the duration.

[0117] For a manufactured secondary source assembly of a specific size, the target nuclide population decays over time after the secondary neutron source assembly is fired out of the reactor. The target nuclide population can only be achieved when the nuclear power unit is exposed to a certain irradiation neutron flux. Therefore, the neutron intensity variation data has a minimum data point. Before the unit's official power increase, the secondary source strength continuously decreases. After startup (official power increase), the secondary source strength increases as the power increases during the unit startup process. When the reactor is just started and in the low-power phase, the source strength is minimum. The minimum data point represents the source strength of the target nuclear reactor at low power. The minimum neutron release intensity is selected from the neutron intensity variation data as the target neutron intensity. Alternatively, the minimum source range meter count is selected from the nuclear instrument count variation data as the target neutron intensity.

[0118] In step S130 of some embodiments, due to the decay characteristics of the secondary source itself and the potential risk of unexpected shutdown of the first reactor of the nuclear power plant, the secondary source strength before critical operation needs to be greater than the minimum source strength requirement. The main risk of secondary source decision-making is that the secondary source has decayed for a long time. For example, after an unexpected shutdown of the reactor at low power, the secondary source strength is too small to provide the reactor with enough monitorable neutrons. In order to ensure the availability of the secondary neutron source assembly, if the target neutron intensity is greater than or equal to the preset neutron intensity threshold, it means that the secondary neutron source assembly can be used as the startup neutron source of the target nuclear reactor. The time step of the target neutron intensity is obtained to obtain the target time, and the loading time window is calculated based on the target time. If the target neutron intensity is less than the preset neutron intensity threshold, it means that the secondary neutron source assembly cannot be used as the startup neutron source of the target nuclear reactor. Then, a secondary neutron source assembly fired in another initial nuclear reactor is selected or the preset risk period is adjusted to update the neutron intensity change data, and the loading time window is calculated based on the updated neutron intensity change data. The preset neutron intensity threshold corresponds to the target neutron intensity. If the target neutron intensity is evaluated using the source range count, the preset neutron intensity threshold also uses the source range count. In this case, the preset neutron intensity threshold is the minimum count that can be monitored by nuclear instrumentation. After the secondary source is loaded, if the secondary source intensity fails to meet the subsequent construction schedule requirements, the target nuclear reactor will need to be unloaded, resulting in excessive startup costs and an unacceptable situation. Therefore, the basic requirement is that the unit does not unload after loading. The preset neutron intensity threshold can be 0.5 cps (count per second) or 0.5 / sensitivity, where / represents division.

[0119] Substituting the preset risk duration in Table 1 or Table 2 into formula (5), we can obtain the neutron intensity change data expressed in the form of a curve after fully considering the risk. After the secondary source loading time of the target nuclear reactor, i.e., the target loading time, is determined, the time interval between the initial time step corresponding to the starting value of the curve (the value of the neutron release intensity when x = 0) and the loading time of the loading platform (the time interval between the loading time and the 0 time step) is affected by the operating unit of the initial nuclear reactor used to fire the secondary neutron source assembly. Selecting different firing units will form different source intensity change curves for the target nuclear reactor. The minimum source range meter number of the source intensity change curve should not be less than 0.5 cps, and this is used as a standard for the preliminary screening of the firing window of the operating unit. The secondary source firing needs to be linked to the overhaul window of the operating unit. Generally, the operating cycle of the operating unit is 12-18 months, while the secondary source firing needs to be decided at least 2 years in advance. The long time span between the two has a large uncertainty, resulting in a high decision difficulty for the secondary source firing. In situations where the construction period for the first reactor is relatively uncertain, multiple sets of secondary neutron source assemblies can be fired to cover the possible operating time period of the unit. This embodiment of the application analyzes the neutron intensity change data of the secondary sources of different fired units after leaving the reactor by considering the impact of factors such as the risk construction period, unit power, and secondary source decay characteristics on the source intensity, thereby reducing the difficulty of decision-making. Secondary neutron source assemblies fired from operating units that meet this standard can be selected for the first cycle startup of the target nuclear reactor.

[0120] It should be noted that secondary sources can only be added to the reactor during the overhaul window of an operating unit and removed from the reactor after the unit completes its operating cycle. Operating units are like shuttle buses for secondary source firing, with fixed boarding and disembarkation times. The selection of units for secondary source firing cannot be separated from the overhaul schedule of the operating units.

[0121] See also Figure 5 In some embodiments, before step S410, the method for starting the nuclear reactor for the first cycle may further include obtaining the startup duration. The specific process of obtaining the startup duration includes but is not limited to steps S510 to S540:

[0122] Step S510, obtaining a first time when a nuclear power unit including a target nuclear reactor is in a first state;

[0123] Step S520, obtaining the current unit power of the nuclear power unit;

[0124] Step S530: If the current unit power is greater than or equal to the preset power threshold, the nuclear power unit is switched from the first state to the second state, and a second time for the nuclear power unit to switch from the first state to the second state is obtained;

[0125] Step S540: Determine the startup duration according to the first time and the second time.

[0126] In step S510 of some embodiments, the first state is a subcritical state or a low power state, and the first time is a time step when the nuclear power unit is in the first state, such as the 14th month after the secondary neutron source assembly is taken out of the reactor.

[0127] In step S520 of some embodiments, the unit power of the nuclear power unit at the current time step is obtained, to obtain the current unit power. The current unit power can be preset according to a preset risk duration.

[0128] In step S530 of some embodiments, the second state is a power-up state, and the unit power of the second state is greater than the unit power of the first state. If the current unit power is greater than or equal to a preset power threshold, it indicates that the nuclear power unit is in a power-up stage, and the nuclear power unit is switched from the first state to the second state. The time step when the nuclear power unit is switched from the first state to the second state is obtained, to obtain the second time. The second time is a time after the secondary neutron source assembly is taken out of the reactor, and the second time is after the first time.

[0129] In step S540 of some embodiments, the second time is subtracted from the first time to obtain the start-up duration. The start-up duration is the duration of the nuclear power unit in the first state.

[0130] Through the above steps S510 to S540, the start-up duration can be obtained to determine the in-pile time window based on the start-up duration.

[0131] Please refer to Figure 6 In some embodiments, step S140 can include but is not limited to steps S610 to S630:

[0132] Step S610, determining a target in-pile time of the secondary neutron source assembly according to the target time and the start-up duration of the target reactor obtained in advance;

[0133] Step S620, obtaining a time when the secondary neutron source assembly is taken out of the initial nuclear reactor to obtain an initial in-pile time;

[0134] Step S630, determining a target in-pile period according to the initial in-pile time and the target in-pile time.

[0135] In step S610 of some embodiments, the target time is subtracted from the start-up duration to obtain the target in-pile time. The target in-pile time is the latest time when the secondary neutron source assembly can be loaded into the target nuclear reactor, such as the 12th month after the secondary neutron source assembly is taken out of the reactor.

[0136] In step S620 of some embodiments, the time when the secondary neutron source assembly is removed from the initial nuclear reactor is obtained to obtain the initial loading time. The initial nuclear reactor is a nuclear reactor used to burn the secondary neutron source assembly and is in stable operation. The initial loading time is the earliest time when the secondary neutron source assembly can be loaded into the target nuclear reactor, and the initial loading time is before the target loading time. The initial loading time is the initial time step, and the initial loading time can be set to 0, indicating the 0th day after the secondary neutron source assembly is taken out of the reactor. That is, after the secondary neutron source assembly is burned out of the reactor, the secondary neutron source assembly is immediately loaded into the target nuclear reactor without considering the limiting factors such as the transportation and decay of the secondary neutron source assembly.

[0137] In step S630 of some embodiments, a target stacking time period is determined based on a time window formed by the initial stacking time and the target stacking time.

[0138] Through the above steps S610 to S630, an accurate loading time window can be determined, the availability of the secondary neutron source assembly is guaranteed, and the target nuclear reactor can be successfully started up for the first cycle.

[0139] See also Figure 7 In some embodiments, step S630 may include but is not limited to steps S710 to S740:

[0140] Step S710, constructing a time interval according to the initial loading time and the target loading time to obtain an initial loading time period;

[0141] Step S720, obtaining a component reference period of a secondary neutron source component; wherein the component reference period is an unavailable period;

[0142] Step S730, adjusting the initial stacking period by a first period according to the component reference period to obtain a reference stacking period;

[0143] Step S740 , adjusting the reference reactor loading period by a second period according to the reactor loading period condition of the target nuclear reactor to obtain a target reactor loading period.

[0144] In step S710 of some embodiments, the initial loading time is used as the left endpoint of the interval, and the target loading time is used as the right endpoint of the interval. A time interval is constructed based on the left and right endpoints of the interval to obtain the initial loading period. The initial loading period is defined by the left and right endpoints of the interval and includes the left and right endpoints of the interval, the right endpoint of the interval, and all time steps between these two endpoints.

[0145] In step S720 of some embodiments, the component reference time period of the secondary neutron source component is obtained, and the component reference time period is a period during which the secondary neutron source component is unavailable due to restrictions. The firing of the secondary source is subject to restrictions such as secondary source manufacturing and transportation, transport containers and transportation requirements. For example, to facilitate the transportation and loading and unloading of the secondary source, the surface radioactive dose of the transport container should be lower than 2mSv / h. After the secondary source is fired out of the pile, it is impossible to transport the secondary source at the first time due to the high intensity of the fired source and the performance of the radiation shielding container. The secondary source needs to decay to a certain intensity before it can be transported. In addition, combined with the time required for transportation itself, there is also an unavailable interval after the secondary source is out of the pile.

[0146] In step S730 of some embodiments, the component reference period is removed from the initial loading period to adjust the initial loading period to obtain a reference loading period. The reference loading period is the available time interval of the secondary neutron source component after taking into account the component reference period.

[0147] In step S740 of some embodiments, the loading period condition is the loading time window required by the target nuclear reactor. The first loading of a nuclear power plant generally has a clear time, but due to many factors such as the large number of nuclear power unit equipment, large construction volume, complex construction and installation logic, and strict external regulatory requirements, it is often necessary to adjust the plan for the first loading time, resulting in a large uncertainty in the first loading time. The firing of secondary sources requires a lead time of 2 years or more. When it is found that no source is available, the best loading decision opportunity has been missed, affecting the startup of the target nuclear reactor. In order to obtain an accurate loading time window, the intersection period of the reference loading period and the time window represented by the loading period condition is selected to obtain the target loading period. For example, if the reference loading period is completely within the time window represented by the loading period condition, the reference loading period is used as the target loading period. If part of the reference loading period is within the time window represented by the loading period condition, the part is used as the target loading period. If the time window represented by the loading period condition is completely within the reference loading period, the time window represented by the loading period condition is used as the target loading period. It should be noted that if multiple operating units are firing secondary neutron source assemblies, the union of multiple target loading periods obtained for these multiple operating units can be selected as the loading time window for the final decision. For example, secondary neutron source assembly 1 and secondary neutron source assembly 2 are fired by two operating nuclear power units at a nuclear power plant, respectively. After obtaining a first target loading period for secondary neutron source assembly 1 and a second target loading period for secondary neutron source assembly 2, the fired secondary neutron source assembly 1 is provided to the nuclear power unit to which the target nuclear reactor belongs during the first target loading period, and the fired secondary neutron source assembly 2 is provided to the nuclear power unit to which the target nuclear reactor belongs during the second target loading period. This ensures that the available interval of the secondary neutron source assemblies fully covers the required loading period, i.e., the loading time window required by the target nuclear reactor. In addition, the secondary source firing range can be expanded to group plants and group piles, and a complete and continuous secondary source availability range can be formed based on the above logic.

[0148] The above steps S710 to S740 ensure the accuracy of the target loading period by eliminating unavailable periods and taking into account the loading time required by the target nuclear reactor, so as to achieve the first cycle startup of the target nuclear reactor.

[0149] In step S150 of some embodiments, the secondary neutron source assembly is loaded into the target nuclear reactor during the target loading period, and the target nuclear reactor is started up for the first time.

[0150] See also Figure 8 The embodiment of the present application further provides a nuclear reactor first cycle startup device, which can implement the above-mentioned nuclear reactor first cycle startup method, and the nuclear reactor first cycle startup device includes:

[0151] A first acquisition module 810 is configured to acquire neutron intensity variation data of a secondary neutron source assembly, wherein the secondary neutron source assembly is an irradiated neutron source assembly, and the neutron intensity variation data includes a time step and a neutron release intensity in the time step, and the neutron intensity variation data is used to characterize a variation trend of the neutron release intensity over the time step;

[0152] A screening module 820 is configured to select the minimum neutron release intensity from the neutron intensity variation data as the target neutron intensity;

[0153] A second acquisition module 830 is configured to acquire a time step of the target neutron intensity to obtain a target time if the target neutron intensity is greater than or equal to a preset neutron intensity threshold;

[0154] A determination module 840 is configured to determine a target time period for loading the secondary neutron source assembly into the reactor based on the target time and a pre-acquired startup duration of the target nuclear reactor;

[0155] The startup module 850 is used to perform an initial cycle startup of the target nuclear reactor according to the target loading period and the secondary neutron source assembly.

[0156] The specific implementation of the nuclear reactor first cycle startup device is basically the same as the specific embodiment of the above-mentioned nuclear reactor first cycle startup method, and will not be repeated here.

[0157] The present application also provides an electronic device comprising a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the above-described method for starting a nuclear reactor for the first cycle. The electronic device can be any smart terminal, including a tablet computer and an in-vehicle computer.

[0158] See also Figure 9 , Figure 9 The hardware structure of an electronic device according to another embodiment is shown. The electronic device includes:

[0159] The processor 910 may be implemented using a general-purpose CPU (Central Processing Unit), a microprocessor, an application-specific integrated circuit (ASIC), or one or more integrated circuits, and is configured to execute relevant programs to implement the technical solutions provided in the embodiments of the present application.

[0160] The memory 920 can be implemented in the form of a Read Only Memory (ROM), a static storage device, a dynamic storage device, or a Random Access Memory (RAM), etc. The memory 920 can store an operating system and other application programs. When the technical solutions provided by the embodiments of the present application are implemented by software or firmware, the related program codes are stored in the memory 920 and are called and executed by the processor 910 to implement the nuclear reactor first cycle startup method of the embodiments of the present application.

[0161] The input / output interface 930 is configured to realize information input and output.

[0162] The communication interface 940 is configured to realize the communication interaction between the device and other devices. The communication can be realized by a wired manner (for example, a USB, a network cable, etc.) or a wireless manner (for example, a mobile network, a WI-FI, a Bluetooth, etc.).

[0163] The bus 950 is configured to transmit information between various components (for example, the processor 910, the memory 920, the input / output interface 930, and the communication interface 940) of the device.

[0164] The processor 910, the memory 920, the input / output interface 930, and the communication interface 940 are connected to each other through the bus 950 to realize the communication connection between the device.

[0165] The embodiments of the present application also provide a computer readable storage medium, which stores a computer program. The computer program is executed by a processor to implement the nuclear reactor first cycle startup method.

[0166] The memory is a non-transitory computer readable storage medium, which can be used to store a non-transitory software program and a non-transitory computer executable program. In addition, the memory can include a high-speed random access memory and can also include a non-transitory memory, for example, at least one magnetic disk storage device, a flash memory device, or other non-transitory solid-state memory device. In some embodiments, the memory can optionally include a memory remotely arranged relative to the processor. These remote memories can be connected to the processor through a network. Examples of the network include but are not limited to the Internet, an intranet, a local area network, a mobile communication network, and a combination thereof.

[0167] The embodiments described in the embodiments of the present application are used to more clearly illustrate the technical solutions of the embodiments of the present application and do not constitute a limitation on the technical solutions provided by the embodiments of the present application. Those skilled in the art can know that, with the evolution of technology and the appearance of new application scenarios, the technical solutions provided by the embodiments of the present application are also applicable to similar technical problems.

[0168] Those skilled in the art can understand that the technical solutions shown in the figures do not constitute a limitation to the embodiments of the present application, and can include more or fewer steps than the figures, or combine certain steps, or different steps.

[0169] The device embodiments described above are merely illustrative, and the units described as separate components can or can not be physically separated, i.e., can be located in one place, or can be distributed to multiple network units. Part or all of the modules can be selected according to actual needs to achieve the purpose of the embodiments.

[0170] Those skilled in the art can understand that all or some of the steps in the above disclosed method, the function modules / units in the system and the device can be implemented as software, firmware, hardware and their appropriate combinations.

[0171] The terms "first", "second", "third", "fourth" and the like (if any) in the specification of the present application and the above-described drawings are used to distinguish similar objects, and do not necessarily have to describe a specific order or sequence. It should be understood that the data thus used can be interchanged under appropriate circumstances, so that the embodiments of the present application described herein can be implemented in an order other than that illustrated or described herein. In addition, the terms "include" and "have" and any variations thereof are intended to cover non-exclusive inclusion, for example, a process, method, system, product or device that includes a series of steps or units does not have to be limited to those steps or units clearly listed, but can include other steps or units not clearly listed or inherent to these processes, methods, products or devices.

[0172] It should be understood that in the present application, "at least one" means one or more, and "multiple" means two or more. "And / or" is used to describe the association between the associated objects, which means that there can be three relationships, for example, "A and / or B" can represent three cases: only A, only B, and A and B exist at the same time, where A and B can be singular or plural. The character " / " generally represents an "or" relationship between the associated objects. "At least one of the following" or similar expressions means any combination of these items, including any combination of single or multiple items. For example, at least one of a, b or c can mean a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, and c can be single or multiple.

[0173] In the several 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 schematic. For example, the division of the above-mentioned units is only a logical function division. In actual implementation, there may be other division methods, such as multiple units or components can be combined or integrated into another system, or some features can be ignored or not executed. The mutual coupling or direct coupling or communication connection shown or discussed can be through some interfaces, indirect coupling or communication connection of devices or units, which can be electrical, mechanical or other forms.

[0174] The units described above as separate components may or may not be physically separate, and the components shown as units may or may not be physical units, that is, they may be located in one place or distributed across multiple network units. Some or all of these units may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0175] In addition, the functional units in the various embodiments of the present application may be integrated into a single processing unit, or each unit may exist physically separately, or two or more units may be integrated into a single unit. The aforementioned integrated units may be implemented in the form of hardware or software functional units.

[0176] If the integrated unit is implemented in the form of a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of the present application is essentially or the part that contributes to the prior art or all or part of the technical solution can be embodied in the form of a software product, and the computer software product is stored in a storage medium, including multiple instructions for enabling a computer device (which can be a personal computer, server, or network device, etc.) to execute all or part of the steps of the methods of various embodiments of the present application. The aforementioned storage medium includes: U disk, mobile hard disk, read-only memory (ROM), random access memory (RAM), disk or optical disk, and other media that can store programs.

[0177] The preferred embodiments of the present invention are described above with reference to the accompanying drawings, but are not intended to limit the scope of the present invention. Any modifications, equivalent substitutions, and improvements made by those skilled in the art without departing from the scope and essence of the present invention should be within the scope of the present invention.

Claims

1. A method for starting up a nuclear reactor for the first cycle, characterized in that: The method comprises: Acquiring neutron intensity variation data of a secondary neutron source assembly; wherein the secondary neutron source assembly is an irradiated neutron source assembly, the neutron intensity variation data includes a time step and a neutron release intensity in the time step, and the neutron intensity variation data is used to characterize a variation trend of the neutron release intensity with the time step; Selecting the minimum neutron release intensity from the neutron intensity variation data as the target neutron intensity; If the target neutron intensity is greater than or equal to a preset neutron intensity threshold, obtaining the time step of the target neutron intensity to obtain a target time; determining a target reactor loading time period for the secondary neutron source assembly based on the target time and a pre-acquired startup duration of the target nuclear reactor; Performing an initial cycle startup of the target nuclear reactor according to the target loading period and the secondary neutron source assembly; Determining the target loading time period of the secondary neutron source assembly according to the target time and the pre-acquired startup time of the target nuclear reactor includes: Determining a target loading time of the secondary neutron source assembly based on the target time and a pre-acquired startup duration of the target reactor; obtaining the time when the secondary neutron source assembly was removed from the initial nuclear reactor to obtain an initial loading time; and determining the target loading time period based on the initial loading time and the target loading time; The determining the target stacking time period according to the initial stacking time and the target stacking time includes: A time interval is constructed according to the initial loading time and the target loading time to obtain an initial loading time period; a component reference time period of the secondary neutron source component is obtained; wherein the component reference time period is an unavailable time period; a first time period adjustment is performed on the initial loading time period according to the component reference time period to obtain a reference loading time period; a second time period adjustment is performed on the reference loading time period according to the loading time period condition of the target nuclear reactor to obtain the target loading time period.

2. The method for starting up a nuclear reactor for the first time according to claim 1, wherein: The secondary neutron source assembly includes a target nuclide, and obtaining neutron intensity change data of the secondary neutron source assembly includes: Get the time step; Acquire the number of nuclides of the target nuclide according to the time step to obtain the target nuclide number; converting the target nuclide quantity into neutron release intensity; The neutron intensity variation data is obtained according to the time step and the neutron release intensity in the time step.

3. The method for starting up a nuclear reactor for the first time according to claim 2, wherein: The acquiring the number of nuclides of the target nuclides according to the time step to obtain the number of target nuclides includes: Acquire the irradiated neutron flux of the target nuclear reactor according to the time step; The target nuclide quantity is obtained by performing nuclide quantity statistics on the time step, the irradiation neutron flux, the pre-acquired decay coefficient of the secondary neutron source component, and the pre-acquired nuclear reaction cross section of the secondary neutron source component through a preset nuclide quantity statistical model.

4. The method for starting up a nuclear reactor for the first time according to claim 3, wherein: The secondary neutron source assembly further includes a first nuclide and a second nuclide, the target nuclide is generated by a nuclear reaction between the first nuclide and the second nuclide, and the preset nuclide quantity statistical model is constructed according to the following steps: Obtaining the nuclide quantity of the first nuclide to obtain an initial nuclide quantity; performing a model analysis on a first preset nuclide quantity change rate model based on the initial nuclide quantity to obtain a first nuclide quantity statistical model; the first preset nuclide quantity change rate model is used to characterize the nuclide quantity change rate of the first nuclide; the first nuclide quantity statistical model is used to count the nuclide quantity of the first nuclide; updating a second preset nuclide quantity change rate model according to the first nuclide quantity statistical model to obtain a third preset nuclide quantity change rate model; the second preset nuclide quantity change rate model is used to characterize the nuclide quantity change rate of the target nuclide; The third preset nuclide quantity change rate model is integrated in the time dimension to obtain the preset nuclide quantity statistical model.

5. The method for starting up a nuclear reactor for the first time according to any one of claims 1 to 4, characterized in that: Before determining the target loading time period of the secondary neutron source assembly according to the target time and the pre-acquired startup duration of the target nuclear reactor, the method for starting up the nuclear reactor for the first time cycle further includes: Obtaining the startup duration includes: Acquiring a first time when a nuclear power unit including the target nuclear reactor is in a first state; Obtaining the current unit power of the nuclear power unit; If the current unit power is greater than or equal to a preset power threshold, switching the nuclear power unit from the first state to a second state, and obtaining a second time for the nuclear power unit to switch from the first state to the second state; The startup duration is determined according to the first time and the second time.

6. A nuclear reactor first cycle startup device, characterized in that: The device comprises: a first acquisition module, configured to acquire neutron intensity variation data of a secondary neutron source assembly; wherein the secondary neutron source assembly is an irradiated neutron source assembly, the neutron intensity variation data including a time step and a neutron release intensity at the time step, the neutron intensity variation data being used to characterize a variation trend of the neutron release intensity with respect to the time step; a screening module, configured to select the minimum neutron release intensity from the neutron intensity variation data as a target neutron intensity; A second acquisition module is configured to acquire the time step of the target neutron intensity to obtain a target time if the target neutron intensity is greater than or equal to a preset neutron intensity threshold; A determination module, configured to determine a target loading time period of the secondary neutron source assembly according to the target time and a pre-acquired startup duration of the target nuclear reactor; a startup module, configured to perform an initial cycle startup of the target nuclear reactor according to the target loading period and the secondary neutron source assembly; The device is also used for: Determining a target loading time of the secondary neutron source assembly based on the target time and a pre-acquired startup duration of the target reactor; obtaining the time when the secondary neutron source assembly was removed from the initial nuclear reactor to obtain an initial loading time; and determining the target loading time period based on the initial loading time and the target loading time; A time interval is constructed according to the initial loading time and the target loading time to obtain an initial loading time period; a component reference time period of the secondary neutron source component is obtained; wherein the component reference time period is an unavailable time period; a first time period adjustment is performed on the initial loading time period according to the component reference time period to obtain a reference loading time period; a second time period adjustment is performed on the reference loading time period according to the loading time period condition of the target nuclear reactor to obtain the target loading time period.

7. An electronic device, characterized in that The electronic device includes a memory and a processor, the memory stores a computer program, and the processor implements the nuclear reactor first cycle startup method according to any one of claims 1 to 5 when executing the computer program.

8. A computer-readable storage medium storing a computer program, characterized in that: When the computer program is executed by a processor, the method for starting up a nuclear reactor for the first cycle according to any one of claims 1 to 5 is implemented.

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