Method, device and equipment for determining core transient neutron flux and storage medium
By calculating the neutron flux rate in the reactor core under unstable conditions, and using shape and amplitude values, the problem of reduced accuracy of neutron flux rate in traditional methods is solved, and accurate calculation of neutron flux rate under unstable conditions is achieved.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- Filing Date
- 2023-04-13
- Publication Date
- 2026-03-20
AI Technical Summary
In unstable conditions, the accuracy of traditional methods for calculating neutron flux in nuclear reactor cores decreases, especially in transient processes caused by changes in control rod positions, where existing factor splitting methods cannot accurately describe the spatial distribution of neutrons with different energies.
By determining the amplitude and shape values based on the neutron flux rate of the reactor core at the previous moment under unstable conditions, and combining them with the neutron flux rate equation, the target neutron flux rate at the current moment is calculated. The shape and amplitude values are introduced to improve the calculation accuracy.
Without significantly increasing the computational load, the accuracy and rationality of the neutron flux rate in the reactor core under unstable conditions were improved, ensuring the reliability of the calculation results.
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Abstract
Description
TECHNICAL FIELD
[0001] The present application relates to the technical field of nuclear reactor core operation and safety, and particularly relates to a method and device for determining a core transient neutron fluence rate, equipment and a storage medium. BACKGROUND
[0002] With the development of industrial technology, nuclear reactors play an increasingly important role in industrial technology, and the core is the core of the nuclear reactor. The safety problem needs to be focused on during the design and operation of the nuclear reactor, and therefore the neutron fluence rate in the transient process of the nuclear reactor core needs to be focused on.
[0003] In the traditional technology, the neutron fluence rate in the nuclear reactor core is generally obtained by solving the time-dependent neutron transport equation or the time-dependent neutron diffusion equation. The main problem is the processing of the time variable, and the specific methods include the direct method and the factor splitting method.
[0004] However, in the non-steady state, for example, the transient process caused by the change of the control rod position, due to the different absorption abilities of the control rod for neutrons of different energies, the spatial distribution of neutrons of different energies changes, resulting in a decrease in the accuracy of the core neutron fluence rate obtained by the traditional factor splitting method. SUMMARY
[0005] Therefore, it is necessary to provide a method and device for determining a core transient neutron fluence rate, equipment and a storage medium for improving the accuracy of the core neutron fluence rate under a reasonable amount of calculation.
[0006] In a first aspect, the present application provides a method for determining a core transient neutron fluence rate. The method comprises:
[0007] In the case that the core is in a non-steady state, determining an amplitude value of the core at a previous time according to a neutron fluence rate of the core at the previous time;
[0008] Determining a shape value and an amplitude value of the core at a current time according to the neutron fluence rate and the amplitude value of the core at the previous time;
[0009] Determining a target neutron fluence rate of the core at the current time according to the shape value and the amplitude value of the core at the current time.
[0010] In one embodiment, determining the amplitude value of the core at the previous time according to the neutron fluence rate of the core at the previous time comprises:
[0011] Extracting an amplitude function related to the energy of the core from a neutron fluence rate equation;
[0012] Determining the amplitude value of the core at the previous time according to the neutron fluence rate of the core at the previous time based on the amplitude function.
[0013] In one of the embodiments, the method further comprises:
[0014] If the previous time is the initial time, the neutron flux of the core in the stable state is taken as the neutron flux of the core at the initial time.
[0015] In one of the embodiments, the shape value and the amplitude value of the core at the current time are determined according to the neutron flux of the core at the previous time and the amplitude value, comprising:
[0016] The current quantization time is determined according to the previous time and the unit time interval;
[0017] The neutron flux equation is discretized by using the current quantization time to obtain the estimated neutron flux of the core at the current time;
[0018] The shape value and the amplitude value of the core at the current time are determined according to the estimated neutron flux of the core at the current time and the amplitude value of the core at the previous time.
[0019] In one of the embodiments, the shape value and the amplitude value of the core at the current time are determined according to the estimated neutron flux of the core at the current time and the amplitude value of the core at the previous time, comprising:
[0020] The amplitude value of the core at the current time is determined according to the estimated neutron flux of the core at the current time based on the neutron flux equation;
[0021] The shape value of the core at the current time is determined according to the amplitude value of the core at the previous time and the amplitude value of the core at the current time.
[0022] In one of the embodiments, the shape value of the core at the current time is determined according to the amplitude value of the core at the previous time and the amplitude value of the core at the current time, comprising:
[0023] The neutron kinetic parameter at the current time is determined according to the amplitude value of the core at the previous time and the amplitude value of the core at the current time;
[0024] The shape value of the core at the current time is determined according to the amplitude value of the core at the previous time, the amplitude value of the core at the current time and the neutron kinetic parameter at the current time.
[0025] In a second aspect, the application further provides a determination device of a core transient neutron flux. The device comprises:
[0026] The first determination module is configured to determine the amplitude value of the core at the previous time according to the neutron flux of the core at the previous time when the core is in a non-stable state;
[0027] The second determining module is configured to determine the shape value and the amplitude value of the reactor core at the current time according to the neutron flux and the amplitude value of the reactor core at the previous time.
[0028] The third determining module is configured to determine the target neutron flux of the reactor core at the current time according to the shape value and the amplitude value of the reactor core at the current time.
[0029] In a third aspect, a computer device is provided. The computer device includes a memory and a processor. The memory stores a computer program. The processor implements the following steps when executing the computer program:
[0030] In a case where the reactor core is in a non-steady state, the amplitude value of the reactor core at the previous time is determined according to the neutron flux of the reactor core at the previous time.
[0031] The shape value and the amplitude value of the reactor core at the current time are determined according to the neutron flux and the amplitude value of the reactor core at the previous time.
[0032] The target neutron flux of the reactor core at the current time is determined according to the shape value and the amplitude value of the reactor core at the current time.
[0033] In a fourth aspect, a computer readable storage medium is provided. The computer readable storage medium stores a computer program. The computer program is executed by a processor to implement the following steps:
[0034] In a case where the reactor core is in a non-steady state, the amplitude value of the reactor core at the previous time is determined according to the neutron flux of the reactor core at the previous time.
[0035] The shape value and the amplitude value of the reactor core at the current time are determined according to the neutron flux and the amplitude value of the reactor core at the previous time.
[0036] The target neutron flux of the reactor core at the current time is determined according to the shape value and the amplitude value of the reactor core at the current time.
[0037] In a fifth aspect, a computer program product is provided. The computer program product includes a computer program. The computer program is executed by a processor to implement the following steps:
[0038] In a case where the reactor core is in a non-steady state, the amplitude value of the reactor core at the previous time is determined according to the neutron flux of the reactor core at the previous time.
[0039] The shape value and the amplitude value of the reactor core at the current time are determined according to the neutron flux and the amplitude value of the reactor core at the previous time.
[0040] The target neutron flux of the reactor core at the current time is determined according to the shape value and the amplitude value of the reactor core at the current time.
[0041] The aforementioned method, apparatus, equipment, and storage medium for determining the transient neutron fluence rate of the reactor core, under unstable conditions, determines the amplitude value of the core at the previous moment based on the neutron fluence rate of the core at the previous moment; then, based on the amplitude value of the previous moment, it determines the shape and amplitude values of the core at the current moment, thereby determining the target neutron fluence rate for the current moment. This scheme, by introducing shape and amplitude values to determine the neutron fluence rate at the current moment, achieves the effect of improving the accuracy and rationality of the core neutron fluence rate in unstable states without significantly increasing the computational load. Attached Figure Description
[0042] Figure 1 This is a flowchart illustrating a method for determining the transient neutron fluence rate in a reactor core in one embodiment.
[0043] Figure 2 This is a flowchart illustrating the process of determining the shape and amplitude values of the reactor core at the current moment in one embodiment.
[0044] Figure 3 This is a flowchart illustrating the process of determining the shape and amplitude values of the core at the current moment in another embodiment;
[0045] Figure 4 This is a flowchart illustrating a method for determining the transient neutron fluence rate in the reactor core in another embodiment;
[0046] Figure 5 This is a structural block diagram of a device for determining the transient neutron fluence rate in a reactor core in one embodiment;
[0047] Figure 6 A structural block diagram of a device for determining the transient neutron fluence rate in the reactor core in another embodiment;
[0048] Figure 7 This is a structural block diagram of the device for determining the transient neutron fluence rate in the reactor core in another embodiment;
[0049] Figure 8 This is an internal structural diagram of a computer device in one embodiment. Detailed Implementation
[0050] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.
[0051] The method for determining the core transient neutron flux provided in the embodiments of the present application can be applied to how to determine the core neutron flux in a non-steady state (i.e., transient state). Optionally, the method can be applied in a server environment. Specifically, in the case that the core of the nuclear reactor is in a non-steady state, the amplitude value at the previous moment is determined according to the neutron flux of the core at the previous moment, and then the shape value and the amplitude value at the current moment are determined to obtain the neutron flux of the core at the current moment. The server can be implemented by an independent server or a server cluster composed of multiple servers.
[0052] In one embodiment, as shown in Figure 1 a method for determining a core transient neutron flux is provided. The embodiments take the method applied to a server as an example. It can be understood that the method can also be applied to a terminal, and can also be applied to a system including a terminal and a server, and can be implemented through the interaction of the terminal and the server. In the embodiments, the method includes the following steps.
[0053] S101, in the case that the core is in a non-steady state, determining the amplitude value of the core at the previous moment according to the neutron flux of the core at the previous moment.
[0054] In the embodiments, the non-steady state is that the core of the nuclear reactor is in a transient state, for example, a transient state of control rod position change. The non-steady state can be divided into multiple moments according to a preset rule, and the time interval between the moments is the same. According to the idea of the quasi-static method, the neutron flux equation can be separated into time and space variables, and the neutron flux equation can be decomposed into a shape function related to the energy of the core and an amplitude function. Optionally, the amplitude value of the core at each moment can be determined by the amplitude function decomposed from the neutron flux equation.
[0055] Optionally, after the neutron flux of the core at the previous moment is determined, the neutron flux equation can be solved according to the neutron flux of the core at the previous moment to obtain the amplitude value of the core at the previous moment.
[0056] One implementation manner is that the amplitude function related to the energy of the core can be extracted from the neutron flux equation; and the amplitude value of the core at the previous moment is determined according to the neutron flux of the core at the previous moment based on the amplitude function.
[0057] The neutron flux equation is a neutron flux equation in a neutron transport kinetics equation set. The neutron transport kinetics equation set is composed of the following formula (1) and formula (2), the formula (1) is the neutron flux equation, and the formula (2) is a delayed neutron precursor concentration equation.
[0058]
[0059]
[0060]
[0061] where ψ g (r,Ω,t) represents the neutron flux; C m (r,t) represents the neutron flux and delayed neutron precursor concentration; r represents a spatial variable, Ω represents an angular variable, and t represents a time variable; G represents the number of energy groups; h and g represent energy group identifiers; M is the number of delayed neutron precursor groups; and m is a delayed neutron group identifier; represents the effective multiplication factor in the transient initial state. The neutron transport kinetics equation set contains various types of neutron cross-section parameters (∑ t represents the macroscopic total cross section, ∑ s represents the macroscopic scattering cross section, v∑ f,h represents the macroscopic neutron production cross section) and neutron kinetics parameters (β represents the delayed neutron fraction, λ represents the delayed neutron precursor decay constant, χ represents the neutron fission spectrum, and v represents the neutron velocity). The superscript p represents prompt neutrons, and the superscript d represents delayed neutrons.
[0062] Further, the neutron flux equation can be decomposed to extract the amplitude function of the core from the neutron flux equation. Specifically, the amplitude function of the core is shown in equation (3):
[0063]
[0064] After obtaining the amplitude function of the core, based on the extracted amplitude function, the neutron flux of the core at the previous time is used to substitute the amplitude function and the neutron flux into the neutron flux equation (i.e., equation (1)) for solving, and thus the amplitude value of the core at the previous time is determined.
[0065] Optionally, if the previous time is the initial time, the neutron flux of the core in the steady state is taken as the neutron flux of the core at the initial time. The initial time is the time when the core of the nuclear reactor is still in the steady state, and in the steady state, the neutron flux is considered not to change with time.
[0066] Specifically, the neutron flux of the core in the steady state can be obtained by solving the neutron transport kinetics equation set, and the neutron flux of the core in the steady state is taken as the neutron flux of the core at the initial time. Further, the neutron flux equation can be decomposed to extract the amplitude function of the core from the neutron flux equation. Based on the amplitude function, the neutron flux of the core at the initial time is assumed to be n g(t0) = 1, the shape function and the neutron flux rate are substituted into the neutron flux rate equation (i.e. formula (1)) to solve, and the amplitude value of the initial time core is determined.
[0067] Further, according to the neutron flux rate of the previous time core, the shape value of the previous time core can also be determined. One implementation manner is that the shape function related to the core energy can be extracted from the neutron flux rate equation; based on the shape function, the shape value of the previous time core is determined according to the neutron flux rate of the previous time core.
[0068] Specifically, the neutron flux rate equation can be decomposed, and the shape function of the core in formula (4) is extracted from the neutron flux rate equation.
[0069]
[0070] After the shape function of the core is obtained, the shape value of the previous time core is determined by solving the neutron flux rate equation based on the extracted shape function according to the neutron flux rate of the previous time core.
[0071] S102, the shape value and the amplitude value of the current time core are determined according to the neutron flux rate and the amplitude value of the previous time core.
[0072] Specifically, after the amplitude value of the previous time core is obtained, the shape value and the amplitude value of the current time core can be solved by a pre-set calculation rule according to the neutron flux rate and the amplitude value of the previous time core in combination with the neutron flux rate equation.
[0073] S103, the target neutron flux rate of the current time core is determined according to the shape value and the amplitude value of the current time core.
[0074] Specifically, after the shape value and the amplitude value of the current time core are determined, the shape value and the amplitude value of the current time core are substituted into the amplitude function (i.e. formula (3)) and the shape function (i.e. formula (4)) respectively, the neutron flux rate equation is solved, and the target neutron flux rate of the current time core is obtained.
[0075] The above method for determining the core transient neutron flux rate determines the amplitude value of the previous time according to the neutron flux rate of the previous time core when the core is in a non-stable state; the shape value and the amplitude value of the current time core are determined according to the amplitude value of the previous time, and then the target neutron flux rate of the current time is determined. The above scheme determines the neutron flux rate of the current time by introducing the shape value and the amplitude value, which realizes the effect of improving the accuracy and rationality of the neutron flux rate of the core in the non-stable state under the premise of little increase in calculation amount.
[0076] In order to improve the accuracy and rationality of the shape value and the amplitude value of the core at the current time, in one embodiment, as shown in Figure 2 The shape value and the amplitude value of the core at the current time can be determined according to the neutron flux rate and the amplitude value of the core at the previous time, specifically as follows:
[0077] S201, determining a current quantization time according to the previous time and a unit time interval.
[0078] In this embodiment, the unit time interval is a pre-set time interval, which is usually smaller than the time interval between each time. The current quantization time is a quantization time value determined according to the previous time and the unit time interval.
[0079] Specifically, according to the pre-set unit time interval, the pre-set unit time interval can be added to the previous time to determine the current quantization time.
[0080] S202, discretizing the neutron flux rate equation using the current quantization time to obtain an estimated neutron flux rate of the core at the current time.
[0081] In this embodiment, the estimated neutron flux rate is a pre-estimated neutron flux rate, which has low accuracy and cannot be used as the target neutron flux rate because the spatial variation of the neutron under the non-steady state is not considered.
[0082] Specifically, after determining the current quantization time, the neutron flux rate equation is discretized using the current quantization time. Optionally, different time discretization methods can be used to discretize the neutron flux rate equation, such as full-implicit time discretization algorithm, semi-implicit time discretization algorithm, etc. Further, after discretizing the neutron flux rate equation, the neutron flux rate of the core at the current time can be calculated, and the calculated neutron flux rate is taken as the estimated neutron flux rate of the core at the current time.
[0083] S203, determining the shape value and the amplitude value of the core at the current time according to the estimated neutron flux rate of the core at the current time and the amplitude value of the core at the previous time.
[0084] Specifically, after obtaining the estimated neutron flux rate of the core at the current time, the amplitude value of the core at the previous time is obtained, and the shape value and the amplitude value of the core at the current time are determined through a pre-set calculation rule.
[0085] It can be understood that the neutron flux equation is discretized by the current quantization time determined according to the previous moment and the preset unit time interval, to obtain the estimated neutron flux of the current moment of the reactor core; and then the shape value and the amplitude value of the current moment of the reactor core are determined in combination with the amplitude value of the previous moment of the reactor core, so that the accuracy and rationality of the shape value and the amplitude value of the current moment of the reactor core are improved, and the accuracy and rationality of the subsequent neutron flux of the current moment of the reactor core are higher.
[0086] In order to make the accuracy and rationality of the shape value and the amplitude value of the current moment of the reactor core higher, in one embodiment, as shown in Figure 3 The shape value and the amplitude value of the current moment of the reactor core can be determined according to the estimated neutron flux of the current moment of the reactor core and the amplitude value of the previous moment of the reactor core, specifically as follows:
[0087] S301, based on the neutron flux equation, the amplitude value of the current moment of the reactor core is determined according to the estimated neutron flux of the current moment of the reactor core.
[0088] Specifically, after obtaining the estimated neutron flux of the current moment of the reactor core, the amplitude value of the current moment of the reactor core can be determined according to the pre-set calculation rule based on the neutron flux equation and using the estimated neutron flux of the current moment of the reactor core.
[0089] One implementation is that the amplitude value of the current moment of the reactor core is determined according to the estimated neutron flux of the current moment of the reactor core based on the neutron flux equation and using the pre-set normalization condition.
[0090] In quantum mechanics, the wave function representing the quantum state of a particle must satisfy the normalization condition, that is, the probability of finding the particle in space must be equal to 1. The normalization condition is shown in formula (5):
[0091]
[0092]
[0093] wherein ψ g (Ω, t)Ω represents an angle variable, t represents a time variable; G represents the number of energy groups; h and g represent energy group identifiers; M is the number of delayed neutron precursor groups; and m is a delayed neutron group identifier. represents the conjugate neutron flux at t0.
[0094] Specifically, after obtaining the estimated neutron flux of the current moment of the reactor core, the amplitude value of the current moment of the reactor core can be determined by solving the neutron flux equation based on the neutron flux equation and using the normalization condition in combination with the estimated neutron flux of the current moment of the reactor core.
[0095] S302, determine the shape value of the core at the current time according to the amplitude value of the core at the previous time and the amplitude value of the core at the current time.
[0096] Specifically, after determining the amplitude value of the core at the current time, the shape value of the core at the current time is determined by combining the determined amplitude value of the core at the previous time and the preset calculation rule.
[0097] In an implementation, the neutron kinetics parameter at the current time is determined according to the amplitude value of the core at the previous time and the amplitude value of the core at the current time; and the shape value of the core at the current time is determined according to the amplitude value of the core at the previous time, the amplitude value of the core at the current time and the neutron kinetics parameter at the current time.
[0098] In the embodiment, the neutron kinetics parameter is an intermediate quantity used to determine the shape value of the core at the current time.
[0099] Specifically, after determining the amplitude value of the core at the current time, the neutron kinetics parameter corresponding to the shape value of the core at the current time can be obtained by combining the amplitude value of the core at the previous time and using the following formulas (6) to (15).
[0100]
[0101]
[0102]
[0103]
[0104]
[0105]
[0106]
[0107]
[0108]
[0109]
[0110] wherein, Δ∑ x = x (t)- x (t0) represents the change of the cross section, wherein the cross section can include but is not limited to total cross section, fission cross section, scattering cross section, etc.; x is the reaction path of the cross section. ψ g (r,Ω,t) represents the neutron fluence rate; C m(r, t) represents the neutron flux and the delayed neutron precursor concentration; r represents the spatial variable, Ω represents the angular variable, and t represents the time variable; G represents the number of energy groups; h and g represent the energy group identification; M is the number of delayed neutron precursor groups; and m is the delayed neutron group identification. represents the effective multiplication factor in the transient initial state.∑ t represents the macroscopic total cross section,∑ s represents the macroscopic scattering interface, v∑ f,h represents the macroscopic neutron production interface. β represents the delayed neutron fraction, λ represents the delayed neutron precursor decay constant, χ represents the neutron fission spectrum, and v represents the neutron velocity.
[0111] Further, after the neutron kinetic parameter corresponding to the amplitude value of the current time core is obtained, according to the amplitude value of the previous time core, the amplitude value of the current time core and the neutron kinetic parameter of the current time, the shape value of the current time core can be determined by using the following formula (16) and formula (17).
[0112]
[0113]
[0114]
[0115] wherein t represents the time variable; G represents the number of energy groups; h and g represent the energy group identification; M is the number of delayed neutron precursor groups; and m is the delayed neutron group identification. β represents the delayed neutron fraction, and λ represents the delayed neutron precursor decay constant.
[0116] It can be understood that the amplitude value of the current time core is determined based on the neutron flux equation through the estimated neutron flux of the current time; further, the shape value of the current time core is determined by combining the amplitude value of the previous time core with the amplitude value of the current time core, which improves the accuracy and rationality of determining the shape value and amplitude value of the current time core, and improves the accuracy and rationality of determining the neutron flux of the current time core.
[0117] In one embodiment, as shown in Figure 4 a preferred example of a method for determining the core transient neutron flux is provided, which specifically comprises:
[0118] S401, in the case that the core is in a non-steady state, extracting an amplitude function related to the core energy from a neutron flux equation.
[0119] S402, based on the amplitude function, determining the amplitude value of the previous time core according to the neutron flux of the previous time core.
[0120] S403, determining a current quantization time according to a previous time and a unit time interval.
[0121] S404, discretizing the neutron fluence rate equation using the current quantization time to obtain an estimated neutron fluence rate of the core at the current time.
[0122] S405, determining an amplitude value of the core at the current time based on the neutron fluence rate equation and the estimated neutron fluence rate of the core at the current time.
[0123] S406, determining a neutron kinetics parameter at the current time according to the amplitude value of the core at the previous time and the amplitude value of the core at the current time.
[0124] S407, determining a shape value of the core at the current time according to the amplitude value of the core at the previous time, the amplitude value of the core at the current time and the neutron kinetics parameter at the current time.
[0125] S408, determining a target neutron fluence rate of the core at the current time according to the shape value and the amplitude value of the core at the current time.
[0126] The specific process of S401-S408 can be referred to the description of the method embodiments, and the implementation principle and technical effects are similar, which will not be repeated here.
[0127] It should be understood that although each step in the flowchart involved in each embodiment as described above is displayed in sequence according to the arrow, these steps are not necessarily executed in sequence according to the arrow. Unless otherwise stated herein, the execution of these steps has no strict order limitation, and these steps can be executed in other order. Moreover, at least part of the steps in the flowchart involved in each embodiment as described above can include multiple steps or stages, which are not necessarily executed at the same time, but can be executed at different times, and the execution order of these steps or stages is not necessarily sequential, but can be alternately executed with other steps or steps or stages in other steps.
[0128] Based on the same inventive concept, the present embodiment also provides a determination device for implementing the determination method of the core transient neutron fluence rate as described above. The implementation scheme for solving the problem provided by the device is similar to the implementation scheme described in the above method, so the specific limitations in one or more core transient neutron fluence rate determination device embodiments provided below can be referred to the limitations of the core transient neutron fluence rate determination method described above, which will not be repeated here.
[0129] In one embodiment, as Figure 5As shown in the figure, a reactor core transient neutron flux determination device 1 is provided, comprising a first determination module 10, a second determination module 20 and a third determination module 30, wherein:
[0130] The first determination module 10 is configured to determine the amplitude value of the reactor core at the previous moment according to the neutron flux of the reactor core at the previous moment when the reactor core is in a non-steady state.
[0131] The second determination module 20 is configured to determine the shape value and the amplitude value of the reactor core at the current moment according to the neutron flux and the amplitude value of the reactor core at the previous moment.
[0132] The third determination module 30 is configured to determine the target neutron flux of the reactor core at the current moment according to the shape value and the amplitude value of the reactor core at the current moment.
[0133] In one embodiment, on the basis of the above Figure 5 , as shown in the figure, the first determination module 10 can comprise: Figure 6
[0134] The first extraction unit 11 is configured to extract the amplitude function related to the reactor core energy from the neutron flux equation.
[0135] The amplitude value determination unit 12 is configured to determine the amplitude value of the reactor core at the previous moment according to the neutron flux of the reactor core at the previous moment based on the amplitude function.
[0136] In one embodiment, the reactor core transient neutron flux determination device 1 can further comprise:
[0137] The initial determination module is configured to, if the previous moment is an initial moment, take the neutron flux of the reactor core in a steady state as the neutron flux of the reactor core at the initial moment.
[0138] In one embodiment, on the basis of the above Figure 5 or Figure 6 , as shown in the figure, the second determination module 20 can comprise: Figure 7 The time determination unit 21 is configured to determine the current quantization time according to the previous moment and the unit time interval.
[0139] The equation discretization unit 22 is configured to discretize the neutron flux equation by using the current quantization time to obtain the estimated neutron flux of the reactor core at the current moment.
[0140] The numerical value determination unit 23 is configured to determine the shape value and the amplitude value of the reactor core at the current moment according to the estimated neutron flux of the reactor core at the current moment and the amplitude value of the reactor core at the previous moment.
[0141]
[0142] In one embodiment, the numerical value determination unit 23 can specifically include:
[0143] The amplitude value determination sub-unit is configured to determine the amplitude value of the core at the current time based on the estimated neutron flux of the core at the current time according to the neutron flux equation.
[0144] The shape value determination sub-unit is configured to determine the shape value of the core at the current time according to the amplitude value of the core at the previous time and the amplitude value of the core at the current time.
[0145] In one embodiment, the shape value determination sub-unit can be specifically configured to:
[0146] determine the neutron kinetic parameter at the current time according to the amplitude value of the core at the previous time and the amplitude value of the core at the current time.
[0147] determine the shape value of the core at the current time according to the amplitude value of the core at the previous time, the amplitude value of the core at the current time, and the neutron kinetic parameter at the current time.
[0148] The modules in the determination device of the core transient neutron flux can be realized by software, hardware, and combinations thereof, in whole or in part. The modules can be embedded in or independent of the processor in the computer device in hardware form, or stored in the memory in the computer device in software form, so as to be called and executed by the processor to perform the operations corresponding to the modules.
[0149] In one embodiment, a computer device is provided, which can be a server, and the internal structure diagram thereof can be as shown in Figure 8 The computer device includes a processor, a memory, and a network interface connected by a system bus. The processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, a computer program, and a database. The internal memory provides an environment for the operating system and the computer program in the non-volatile storage medium to run. The database of the computer device is configured to store data such as the neutron flux of the core at the previous time, the shape value and the amplitude value of the core at the previous time. The network interface of the computer device is configured to communicate with the external terminal through the network connection. The computer program is executed by the processor to implement a determination method of a core transient neutron flux.
[0150] Those skilled in the art can understand that Figure 8 The structure shown in the figure is only a block diagram of part of the structure related to the scheme of the present application, and does not constitute a limitation on the computer device to which the scheme of the present application is applied. The specific computer device can include more or fewer components than those shown in the figure, or combine certain components, or have a different arrangement of components.
[0151] In one embodiment, a computer device is provided, comprising a memory and a processor, the memory storing a computer program, the processor implementing the following steps when executing the computer program:
[0152] In the case that the reactor core is in a non-steady state, determining an amplitude value of the reactor core at a previous time according to a neutron flux of the reactor core at the previous time;
[0153] Determining a shape value and the amplitude value of the reactor core at a current time according to the neutron flux and the amplitude value of the reactor core at the previous time;
[0154] Determining a target neutron flux of the reactor core at the current time according to the shape value and the amplitude value of the reactor core at the current time.
[0155] In one embodiment, the processor, when implementing the logic of determining the amplitude value of the reactor core at the previous time according to the neutron flux of the reactor core at the previous time, also implements the following steps:
[0156] Extracting an amplitude function related to a reactor core energy from a neutron flux equation;
[0157] Determining the amplitude value of the reactor core at the previous time according to the neutron flux of the reactor core at the previous time based on the amplitude function.
[0158] In one embodiment, the processor, when executing the computer program, also implements the following steps:
[0159] If the previous time is an initial time, taking a neutron flux of the reactor core in a steady state as the neutron flux of the reactor core at the initial time.
[0160] In one embodiment, the processor, when implementing the logic of determining the shape value and the amplitude value of the reactor core at the current time according to the neutron flux and the amplitude value of the reactor core at the previous time, also implements the following steps:
[0161] Determining a current quantization time according to the previous time and a unit time interval;
[0162] Discretizing the neutron flux equation using the current quantization time to obtain an estimated neutron flux of the reactor core at the current time;
[0163] Determining the shape value and the amplitude value of the reactor core at the current time according to the estimated neutron flux of the reactor core at the current time and the amplitude value of the reactor core at the previous time.
[0164] In one embodiment, the processor, when implementing the logic of determining the shape value and the amplitude value of the reactor core at the current time according to the estimated neutron flux of the reactor core at the current time and the amplitude value of the reactor core at the previous time, also implements the following steps:
[0165] The amplitude value of the current time core is determined based on the neutron flux equation and the estimated neutron flux of the current time core;
[0166] The shape value of the current time core is determined according to the amplitude value of the previous time core and the amplitude value of the current time core.
[0167] In one embodiment, the processor executes the computer program to determine the shape value of the current time core according to the amplitude value of the previous time core and the amplitude value of the current time core, and also implements the following steps:
[0168] The neutron kinetic parameter of the current time is determined according to the amplitude value of the previous time core and the amplitude value of the current time core;
[0169] The shape value of the current time core is determined according to the amplitude value of the previous time core, the amplitude value of the current time core and the neutron kinetic parameter of the current time.
[0170] In one embodiment, a computer readable storage medium is provided, and the computer readable storage medium stores a computer program, and the computer program is executed by a processor to implement the following steps:
[0171] In the case that the core is in a non-steady state, the amplitude value of the previous time core is determined according to the neutron flux of the previous time core;
[0172] The shape value and the amplitude value of the current time core are determined according to the neutron flux and the amplitude value of the previous time core;
[0173] The target neutron flux of the current time core is determined according to the shape value and the amplitude value of the current time core.
[0174] In one embodiment, the computer program determines the amplitude value of the previous time core according to the neutron flux of the previous time core, and the processor executes the computer program to implement the following steps:
[0175] The amplitude function related to the core energy is extracted from the neutron flux equation;
[0176] The amplitude value of the previous time core is determined according to the neutron flux of the previous time core based on the amplitude function.
[0177] In one embodiment, the computer program is executed by the processor to implement the following steps:
[0178] If the previous time is the initial time, the neutron flux of the core in the steady state is taken as the neutron flux of the initial time core.
[0179] In one embodiment, the computer program, when executed by the processor, implements the following steps in addition to determining the shape value and the amplitude value of the core at the current time based on the neutron flux of the core at the previous time and the amplitude value:
[0180] determining the current quantization time according to the previous time and the unit time interval;
[0181] discretizing the neutron flux equation using the current quantization time to obtain the estimated neutron flux of the core at the current time;
[0182] determining the shape value and the amplitude value of the core at the current time based on the estimated neutron flux of the core at the current time and the amplitude value of the core at the previous time.
[0183] In one embodiment, the computer program, when executed by the processor, implements the following steps in addition to determining the shape value and the amplitude value of the core at the current time based on the estimated neutron flux of the core at the current time and the amplitude value of the core at the previous time:
[0184] determining the amplitude value of the core at the current time based on the estimated neutron flux of the core at the current time according to the neutron flux equation;
[0185] determining the shape value of the core at the current time based on the amplitude value of the core at the previous time and the amplitude value of the core at the current time.
[0186] In one embodiment, the computer program, when executed by the processor, implements the following steps in addition to determining the shape value of the core at the current time based on the amplitude value of the core at the previous time and the amplitude value of the core at the current time:
[0187] determining the neutron kinetic parameter at the current time based on the amplitude value of the core at the previous time and the amplitude value of the core at the current time;
[0188] determining the shape value of the core at the current time based on the amplitude value of the core at the previous time, the amplitude value of the core at the current time, and the neutron kinetic parameter at the current time.
[0189] In one embodiment, a computer program product is provided, comprising a computer program which, when executed by a processor, implements the following steps:
[0190] determining the amplitude value of the core at the previous time based on the neutron flux of the core at the previous time when the core is in a non-steady state;
[0191] determining the shape value and the amplitude value of the core at the current time based on the neutron flux of the core at the previous time and the amplitude value;
[0192] determining the target neutron flux of the core at the current time based on the shape value and the amplitude value of the core at the current time.
[0193] In one embodiment, the computer program, when executed by the processor, implements the following steps in addition to the logic of determining the amplitude value of the previous moment core based on the neutron flux of the previous moment core:
[0194] extracting the amplitude function related to the core energy from the neutron flux equation;
[0195] determining the amplitude value of the previous moment core based on the neutron flux of the previous moment core based on the amplitude function.
[0196] In one embodiment, the computer program, when executed by the processor, implements the following steps in addition to the logic of determining the amplitude value of the previous moment core based on the neutron flux of the previous moment core:
[0197] If the previous moment is the initial moment, the neutron flux of the core in the steady state is taken as the neutron flux of the core at the initial moment.
[0198] In one embodiment, the computer program, when executed by the processor, implements the following steps in addition to the logic of determining the shape value and amplitude value of the current moment core based on the neutron flux and amplitude value of the previous moment core:
[0199] determining the current quantization time according to the previous moment and the unit time interval;
[0200] discretizing the neutron flux equation using the current quantization time to obtain the estimated neutron flux of the core at the current moment;
[0201] determining the shape value and amplitude value of the core at the current moment based on the estimated neutron flux of the core at the current moment and the amplitude value of the core at the previous moment.
[0202] In one embodiment, the computer program, when executed by the processor, implements the following steps in addition to the logic of determining the shape value and amplitude value of the current moment core based on the estimated neutron flux of the core at the current moment and the amplitude value of the core at the previous moment:
[0203] determining the amplitude value of the core at the current moment based on the estimated neutron flux of the core at the current moment based on the neutron flux equation;
[0204] determining the shape value of the core at the current moment based on the amplitude value of the core at the previous moment and the amplitude value of the core at the current moment.
[0205] In one embodiment, the computer program, when executed by the processor, implements the following steps in addition to the logic of determining the shape value of the core at the current moment based on the amplitude value of the core at the previous moment and the amplitude value of the core at the current moment:
[0206] determining the neutron kinetic parameter at the current moment based on the amplitude value of the core at the previous moment and the amplitude value of the core at the current moment;
[0207] According to the amplitude value of the previous moment of the reactor core, the amplitude value of the current moment of the reactor core and the neutron dynamic parameter of the current moment, the shape value of the current moment of the reactor core is determined.
[0208] It should be noted that the data involved in the present application (including but not limited to the neutron fluence rate of the previous moment of the reactor core, the shape value and amplitude value of the previous moment of the reactor core, etc.) are all authorized or fully authorized information and data.
[0209] Those skilled in the art can understand that all or part of the processes in the above-mentioned embodiment methods can be completed by a computer program instructing related hardware. The computer program can be stored in a non-volatile computer readable storage medium. When the computer program is executed, it can include the processes of the above-mentioned embodiments. Any reference to memory, database or other medium used in the embodiments provided by the present application can include at least one of non-volatile and volatile memory. Non-volatile memory can include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical storage, high-density embedded non-volatile memory, resistive memory (ReRAM), magnetic variable memory (Magnetoresistive Random Access Memory, MRAM), ferroelectric memory (Ferroelectric Random Access Memory, FRAM), phase change memory (Phase Change Memory, PCM), graphene memory, etc. Volatile memory can include random access memory (RAM) or external cache memory, etc. As an illustration but not limitation, RAM can be in various forms, such as static random access memory (SRAM) or dynamic random access memory (DRAM), etc. The database involved in the embodiments provided by the present application can include at least one of a relational database and a non-relational database. The non-relational database can include a distributed database based on a block chain, etc., without being limited thereto. The processor involved in the embodiments provided by the present application can be a general-purpose processor, a central processing unit, a graphics processing unit, a digital signal processor, a programmable logic device, a data processing logic device based on quantum computing, etc., without being limited thereto.
[0210] The technical features of the above embodiments can be combined arbitrarily. In order to make the description simple, not all possible combinations of the technical features in the above embodiments are described, however, as long as the combination of the technical features does not exist contradictory, it should be considered as the scope of the present application.
[0211] The above-described embodiments are merely illustrative of several embodiments of the present application, which are described in more detail and in a specific manner, but should not be construed as limiting the scope of the patent of the present application. It should be noted that, for those of ordinary skill in the art, several modifications and improvements can be made without departing from the concept of the present application, and these all belong to the protection scope of the present application. Therefore, the protection scope of the present application should be subject to the appended claims.
Claims
1. A method for determining the transient neutron fluence rate in a reactor core, characterized in that, The method includes: When the core is in an unstable state, an amplitude function related to the core energy is extracted from the neutron flux rate equation, and based on the amplitude function, the amplitude value of the core at the previous moment is determined according to the neutron flux rate of the core at the previous moment. The current quantization time is determined based on the previous moment and the unit time interval. Using the current quantization time, the neutron flux rate equation is discretized to obtain the estimated neutron flux rate of the reactor core at the current time; Based on the neutron flux rate equation, the amplitude value of the core at the current moment is determined according to the estimated neutron flux rate of the core at the current moment; Based on the amplitude value of the core at the previous moment and the amplitude value of the core at the current moment, the neutron dynamics parameters at the current moment are determined. The shape value of the core at the current moment is determined based on the amplitude value of the core at the previous moment, the amplitude value of the core at the current moment, and the neutron dynamics parameters at the current moment. Based on the shape and amplitude values of the core at the current moment, the target neutron flux rate of the core at the current moment is determined.
2. The method according to claim 1, characterized in that, The method further includes: If the previous moment is the initial moment, then the neutron flux rate of the core in a stable state is taken as the neutron flux rate of the core at the initial moment.
3. The method according to claim 1, characterized in that, Determining the current quantization time based on the previous moment and the unit time interval includes: The previous time is added to the unit time interval to obtain the current quantized time.
4. The method according to claim 1, characterized in that, The determination of the amplitude value of the core at the current moment based on the neutron flux rate equation and the estimated neutron flux rate of the core at the current moment includes: Based on the neutron flux rate equation, and according to the estimated neutron flux rate of the core at the current moment, the amplitude value of the core at the current moment is determined using a pre-set normalization condition.
5. The method according to claim 1, characterized in that, The step of determining the target neutron flux rate of the core at the current moment based on the shape and amplitude values of the core at the current moment includes: The shape and amplitude values of the core at the current moment are substituted into the shape function and amplitude function, respectively, to solve the neutron flux rate equation and obtain the target neutron flux rate of the core at the current moment.
6. A device for determining the transient neutron fluence rate of a reactor core, characterized in that, The device includes: The first determining module is used to determine the amplitude value of the core at the previous moment based on the neutron flux rate of the core at the previous moment when the core is in an unstable state. The second determining module is used to determine the shape and amplitude values of the core at the current moment based on the amplitude value of the core at the previous moment. The third determining module is used to determine the target neutron flux rate of the core at the current moment based on the shape value and amplitude value of the core at the current moment; The second determining module includes: A time determination unit is used to determine the current quantization time based on the previous moment and the unit time interval; The equation discretization unit is used to discretize the neutron flux rate equation using the current quantization time to obtain the estimated neutron flux rate of the reactor core at the current time. The numerical determination unit is used to determine the amplitude value of the core at the current moment based on the neutron flux rate equation and the estimated neutron flux rate of the core at the current moment; to determine the neutron dynamics parameters at the current moment based on the amplitude value of the core at the previous moment and the amplitude value of the core at the current moment; and to determine the shape value of the core at the current moment based on the amplitude value of the core at the previous moment, the amplitude value of the core at the current moment, and the neutron dynamics parameters at the current moment. The first determination module includes: The first extraction unit is used to extract the amplitude function related to the core energy from the neutron flux rate equation; The amplitude value determination unit is used to determine the amplitude value of the core at the previous moment based on the amplitude function and the neutron flux rate of the core at the previous moment.
7. A computer device comprising a memory and a processor, wherein the memory stores a computer program, characterized in that, When the processor executes the computer program, it implements the steps of the method according to any one of claims 1 to 5.
8. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by a processor, it implements the steps of the method according to any one of claims 1 to 5.
9. A computer program product, comprising a computer program, characterized in that, When the computer program is executed by a processor, it implements the steps of the method according to any one of claims 1 to 5.