Fuel element damage monitoring method and device based on delayed neutron energy spectrum measurement

Abstract

The invention relates to a fuel element damage monitoring method and device based on delayed neutron energy spectrum measurement. The method comprises the following steps: acquiring a delayed neutron zone for fuel element damage monitoring; according to the delayed neutron partition and the delayed neutron partition multi-column energy spectrum measurement principle, a moderator for fuel element damage monitoring is obtained; according to the moderation body and a discrimination threshold automatic identification algorithm, determining a discrimination threshold value of fuel element damage monitoring; and according to the discrimination threshold value, a few-channel spectrum unfolding algorithm and an energy spectrum peak searching algorithm, identifying neutron energy spectrum change conditions and delayed neutron precursor nuclides of fuel element damage monitoring. According to the invention, on-line real-time measurement of the delayed neutron energy spectrum can be realized, and the neutron energy spectrum change condition can be determined; according to the invention, when the delayed neutron precursor nuclide is identified, the occurrence of effective fuel element damage is judged, the online monitoring of the fast reactor fuel element damage is realized, and the rapidness and timeliness of fuel damage monitoring are improved.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear reactors, and more specifically, to a method and device for monitoring fuel element damage based on delayed neutron spectrum measurement. Background Art

[0002] When ensuring the radioactive safety of nuclear reactors, fast reactors in various countries require that under normal operating conditions, a large number of fuel element seals are not allowed to be damaged or large fuel element cladding is not allowed to be damaged. When the damage to the fuel element seal exceeds the allowable limit, the primary circuit coolant and covering gas may be contaminated by fission products, and the nuclear fuel may fall into the primary circuit. In addition, due to the increase in fuel power line density and burnup, the performance of fuel and cladding in sodium-cooled fast reactors has always received high attention. Fuel damage monitoring occupies an important position in fast reactor safety. The fuel damage online monitoring system is required to quickly and effectively provide information on core fuel cladding damage.

[0003] The existing fast reactor delayed neutron monitoring system is a subsystem of the fuel damage monitoring system, which is used to monitor the delayed neutron intensity in the primary loop sodium to determine whether the fuel cladding has contact damage, so as to take necessary measures to prevent further damage. The system directly arranges the delayed neutron detection station near the intermediate heat exchanger, and uses the flow of the primary loop sodium to transport the delayed neutron precursor nuclei that may leak from the damaged fuel to the intermediate heat exchanger and release the delayed neutrons for detection.

[0004] Since the delayed neutron precursor nucleus takes a long time to be transported from the damaged fuel to the intermediate heat exchanger, and the half-life of the delayed neutron precursor nucleus is relatively short, the intensity of the delayed neutrons released near the intermediate heat exchanger is relatively weak. 87 Br and 137 In the case of I, theoretically 1cm 2 The neutron flux rate at the delayed neutron detector caused by cladding damage is only close to 12cm -2 ·s -1 , however, the background neutron injection rate here can reach 3700cm -2 ·s -1 According to national standards, the delayed neutron injection rate at the neutron detector must be greater than ( =Background neutron injection rate) can measure effective delayed neutron signals from background signals. That is, if the existing delayed neutron monitoring system can theoretically monitor effective fuel element damage signals, the minimum fuel damage area must reach 15cm 2 Or above, but in actual engineering applications, this value may be even larger, which poses a greater risk to the safe application of fast reactors. Summary of the invention

[0005] The embodiments of the present application provide a method and device for monitoring fuel element damage based on delayed neutron spectrum measurement. In order to have a basic understanding of some aspects of the disclosed embodiments, a simple summary is given below. This summary is not a general review, nor is it intended to identify key / important components or describe the scope of protection of these embodiments. Its only purpose is to present some concepts in a simple form as a preface to the detailed description that follows.

[0006] In a first aspect, the present application provides a fuel element damage monitoring method based on delayed neutron spectrum measurement, the method comprising:

[0007] Obtaining delayed neutron partitions for fuel element damage monitoring;

[0008] According to the delayed neutron partition and delayed neutron partition multi-column spectrum measurement principle, a moderator for monitoring the damage of the fuel element is obtained;

[0009] Determining the discrimination threshold for monitoring damage of the fuel element according to the moderator and discrimination threshold automatic identification algorithm;

[0010] According to the discrimination threshold, the few-channel spectrum analysis algorithm and the spectrum peak search algorithm, the neutron spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified.

[0011] According to a preferred embodiment, the determining the discrimination threshold for monitoring the damage of the fuel element according to the moderator and the discrimination threshold automatic identification algorithm comprises:

[0012] According to the moderator and modeling simulation analysis, a neutron energy response function of the detector for monitoring the damage of the fuel element is obtained;

[0013] The discrimination threshold for monitoring the damage of the fuel element is determined according to the neutron energy response function of the detector and the automatic discrimination threshold identification algorithm.

[0014] According to a preferred embodiment, the method of determining the discrimination threshold for monitoring fuel element damage according to the detector neutron energy response function and the discrimination threshold automatic identification algorithm includes:

[0015] According to the detector neutron energy response function and the threshold time-sharing automatic scanning method for generating a discrimination threshold curve, constructing the discrimination threshold curve for monitoring the damage of the fuel element;

[0016] Determining a discrimination threshold for monitoring damage of the fuel element according to the discrimination threshold curve and the digital signal processing algorithm;

[0017] The method of automatically scanning the threshold value in time-sharing to generate a discrimination threshold curve and the digital signal processing algorithm are used as the automatic discrimination threshold recognition algorithm.

[0018] According to a preferred embodiment, the identification of the neutron spectrum change and delayed neutron precursor nuclides for the fuel element damage monitoring based on the discrimination threshold, the few-channel spectrum analysis algorithm and the spectrum peak search algorithm includes:

[0019] Obtaining a delayed neutron energy spectrum for monitoring damage of the fuel element according to the discrimination threshold and the few-channel spectrum analysis algorithm;

[0020] According to the delayed neutron energy spectrum and the energy spectrum peak-finding algorithm, the neutron energy spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified.

[0021] According to a preferred embodiment, the few-channel spectral analysis algorithm includes: training of a neural network model.

[0022] In a second aspect, the present application provides a fuel element damage monitoring device based on delayed neutron spectrum measurement, the device comprising:

[0023] An acquisition module, used to acquire delayed neutron partitions for fuel element damage monitoring;

[0024] A moderator determination module, used for obtaining the moderator for monitoring the damage of the fuel element according to the delayed neutron partition and the delayed neutron partition multi-column spectrum measurement principle;

[0025] A discrimination threshold determination module, used to determine the discrimination threshold for monitoring the damage of the fuel element according to the moderator and the discrimination threshold automatic identification algorithm;

[0026] The identification module is used to identify the neutron spectrum changes and delayed neutron precursor nuclides for the fuel element damage monitoring according to the discrimination threshold, the few-channel spectrum analysis algorithm and the energy spectrum peak search algorithm.

[0027] According to a preferred embodiment, the discrimination threshold determination module is specifically used for:

[0028] An analysis unit, configured to obtain a neutron energy response function of the detector for monitoring damage of the fuel element according to the moderator and modeling simulation analysis;

[0029] A determination unit is used to determine the discrimination threshold for monitoring the damage of the fuel element according to the neutron energy response function of the detector and the automatic discrimination threshold recognition algorithm.

[0030] According to a preferred embodiment, the determining unit is specifically configured to:

[0031] According to the detector neutron energy response function and the threshold time-sharing automatic scanning method for generating a discrimination threshold curve, constructing the discrimination threshold curve for monitoring the damage of the fuel element;

[0032] Determining a discrimination threshold for monitoring damage of the fuel element according to the discrimination threshold curve and the digital signal processing algorithm;

[0033] The method of automatically scanning the threshold value in time-sharing to generate a discrimination threshold curve and the digital signal processing algorithm are used as the discrimination threshold automatic identification algorithm.

[0034] According to a preferred embodiment, the identification module is specifically used for:

[0035] Obtaining a delayed neutron energy spectrum for monitoring damage of the fuel element according to the discrimination threshold and the few-channel spectrum analysis algorithm;

[0036] According to the delayed neutron energy spectrum and the energy spectrum peak-finding algorithm, the neutron energy spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified.

[0037] According to a preferred embodiment, the few-channel spectral analysis algorithm includes: training of a neural network model.

[0038] In a third aspect, the present application provides a computer storage medium, which stores a plurality of instructions, and the instructions are suitable for being loaded by a processor and executing the above-mentioned method steps.

[0039] In a fourth aspect, the present application provides a terminal, which may include: a processor and a memory; wherein the memory stores a computer program, and the computer program is suitable for being loaded by the processor and executing the above-mentioned method steps.

[0040] The technical solution provided by this application may have the following beneficial effects:

[0041] In the present application, the fuel element damage monitoring method based on delayed neutron spectrum measurement obtains the delayed neutron partition for fuel element damage monitoring; according to the delayed neutron partition and the delayed neutron partition multi-column spectrum measurement principle, the moderator for the fuel element damage monitoring is obtained; according to the moderator and the automatic identification algorithm of the discrimination threshold, the discrimination threshold for the fuel element damage monitoring is determined; according to the discrimination threshold, the few-channel spectrum analysis algorithm and the spectrum peak search algorithm, the neutron spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified. In view of the shortcomings of the above-mentioned background technology, the present application proposes a fuel element damage monitoring method based on delayed neutron spectrum measurement by analyzing and mastering the release mechanism of fission products under the damage of fast reactor fuel cladding, so as to judge the effective delayed neutron signal when a small break occurs in the fuel element. The present application adopts the automatic identification algorithm of the discrimination threshold to realize the online real-time measurement of the delayed neutron spectrum, realizes the online monitoring of the damage of fast reactor fuel elements, and improves the speed and timeliness of fuel damage monitoring. The present application uses the Shaodao spectrum analysis algorithm to solve the delayed neutron spectrum in real time. The energy spectrum peak search algorithm is used to analyze the changes in the delayed neutron energy region in the energy spectrum and identify the elements at different peak positions. The changes in the neutron spectrum can be determined. When the delayed neutron precursor nuclides are identified by the energy spectrum peak search algorithm, it is determined that effective fuel element damage has occurred. The method described in the present application can theoretically reduce the minimum damage area of ​​the monitored fuel to 1cm 2 or less, which solves the problem that the delayed neutron injection rate at the neutron detector must be increased to more than Only then can the defects with effective delayed neutron signals be measured from the background.

[0042] It is to be understood that the foregoing general description and the following detailed description are exemplary and explanatory only and are not restrictive of the invention. BRIEF DESCRIPTION OF THE DRAWINGS

[0043] The accompanying drawings, which are incorporated in and constitute a part of this specification, illustrate embodiments consistent with the invention and, together with the description, serve to explain the principles of the invention.

[0044] Figure 1 It is a flow chart of a fuel element damage monitoring method based on delayed neutron spectrum measurement provided in an embodiment of the present application;

[0045] Figure 2 It is a delayed neutron spectrum distribution diagram of whether there is fuel damage in a fuel element damage monitoring method based on delayed neutron spectrum measurement provided in an embodiment of the present application;

[0046] Figure 3 It is a structural schematic diagram of a fuel element damage monitoring device based on delayed neutron spectrum measurement provided in an embodiment of the present application;

[0047] Figure 4 It is a structural diagram of a terminal provided in an embodiment of the present application.

[0048] Reference numerals:

[0049] 10000, acquisition module, 20000, slowing body determination module, 30000, discrimination threshold determination module, 40000, identification module;

[0050] 1001. Processor, 1002. Communication bus, 1003. User interface, 1004. Network interface, 1005. Memory. DETAILED DESCRIPTION

[0051] The following description and the drawings sufficiently illustrate specific embodiments of the invention to enable those skilled in the art to practice them.

[0052] It should be clear that the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0053] When the following description refers to the drawings, unless otherwise indicated, the same numbers in different drawings represent the same or similar elements. The embodiments described in the following exemplary embodiments do not represent all embodiments consistent with the present invention. Instead, they are only examples of systems and methods consistent with some aspects of the present invention as detailed in the attached claims.

[0054] In the description of the present invention, it should be understood that the terms "first", "second", etc. are only used for descriptive purposes and cannot be understood as indicating or implying relative importance. For those of ordinary skill in the art, the specific meanings of the above terms in the present invention can be understood according to specific circumstances. In addition, in the description of the present invention, unless otherwise specified, "plurality" refers to two or more. "And / or" describes the association relationship of associated objects, indicating that three relationships may exist. For example, A and / or B can represent: A exists alone, A and B exist at the same time, and B exists alone. The character " / " generally indicates that the previously associated objects are in an "or" relationship.

[0055] The following will be combined with the attached Figure 1 and attached Figure 2 , a fuel element damage monitoring method based on delayed neutron spectrum measurement provided in an embodiment of the present application is introduced in detail.

[0056] See also Figure 1 and 2 The method of the embodiment of the present application may include the following steps:

[0057] The present application proposes a fuel element damage monitoring method based on delayed neutron spectrum measurement. This method is based on the defects of the existing fast reactor fuel damage delayed neutron monitoring system. It is a fuel element damage monitoring method that can quickly and online monitor the delayed neutron spectrum and accurately determine the degree of fuel element damage. It is an online fuel element damage monitoring method based on the real-time measurement of the delayed neutron spectrum with an automatic recognition algorithm based on a discrimination threshold. In the present application, the use of neutron detectors can better fit the reactor structure, increase the effective detection contact range, and improve the neutron sensitive response to meet the needs of fast and accurate spectrum measurement. The present application can theoretically reduce the minimum damage area of ​​the monitored fuel to 1cm 2 or less, which solves the problem that the delayed neutron injection rate at the neutron detector must be increased to more than Only in this way can the defects of effective delayed neutron signals be measured from the background, and online monitoring of fast reactor fuel element damage be achieved, providing advanced technical means for the safe operation, accident handling and emergency response of fast reactors. is the background neutron injection rate.

[0058] The fuel element damage monitoring method based on delayed neutron spectrum measurement described in the embodiment of the present application is mainly based on the delayed neutron partition multi-column spectrum measurement principle, the automatic identification algorithm of the discrimination threshold, the development and training of the few-channel spectrum analysis algorithm and the spectrum peak search algorithm. The details are as follows:

[0059] S100, obtaining delayed neutron partitions for fuel element damage monitoring.

[0060] In the embodiment of the present application, the delayed neutron partition of the delayed neutron online monitoring system may be m partitions, and the m partitions may be four partitions, five partitions or six partitions, etc. The larger the m value of the m partition, the smoother the measured delayed neutron energy spectrum.

[0061] S200, obtaining a moderator for monitoring damage of the fuel element according to the delayed neutron partitioning and delayed neutron partitioning multi-column spectrum measurement principle.

[0062] In the embodiment of the present application, the principle of delayed neutron zoned multi-column energy spectrum measurement is as follows: in different zones, a multi-pillar boron-coated proportional counter tube detector is used as a neutron sensitive detection element, and each neutron detector is wrapped with a moderator of different thicknesses. The multi-pillar boron-coated proportional counter tube detector is used as a neutron detection sensitive element to achieve high-sensitivity neutron detection under a strong gamma background.

[0063] The multi-pillar boron-coated proportional counter tube detector is a neutron detector; the moderator is a high molecular weight polyethylene column.

[0064] In the embodiment of the present application, moderators of different thicknesses are applied to the n neutron detectors in each delayed neutron partition. In this case, a relatively rough neutron energy distribution can be obtained in theory.

[0065] S300, determining the discrimination threshold for monitoring damage of the fuel element according to the moderator and the discrimination threshold automatic identification algorithm, including:

[0066] According to the moderator and modeling simulation analysis, a neutron energy response function of the detector for monitoring the damage of the fuel element is obtained;

[0067] Determining the discrimination threshold for monitoring the damage of the fuel element according to the detector neutron energy response function and the discrimination threshold automatic identification algorithm specifically includes:

[0068] According to the detector neutron energy response function and the threshold time-sharing automatic scanning method for generating a discrimination threshold curve, a discrimination threshold curve for monitoring fuel element damage is constructed; according to the discrimination threshold curve and the digital signal processing algorithm, the discrimination threshold for monitoring fuel element damage is determined; the threshold time-sharing automatic scanning method for generating a discrimination threshold curve and the digital signal processing algorithm are used as the discrimination threshold automatic identification algorithm.

[0069] In the embodiment of the present application, the different thicknesses of the moderator are determined by modeling and simulation analysis, and the detector neutron energy response function corresponding to the moderators of different thicknesses is obtained, so that the neutron detectors in different moderators are sensitive to neutrons of different energies. According to the detector neutron energy response function, the neutron nuclear pulse signal is determined. Modeling and simulation analysis is a specific simulation software such as MCNP, GEANT4, etc.; through this specific simulation software, the energy response function of neutrons of different energies after being slowed down by moderators of different thicknesses, that is, the detector neutron energy response function, can be calculated.

[0070] In the embodiment of the present application, the process of generating a discrimination threshold curve by using a threshold time-sharing automatic scanning method is as follows: by counting the neutron nuclear pulse signal, determining the pulse measurement number corresponding to each of the multiple energy channel value distribution points corresponding to the count value of the neutron nuclear pulse signal and the preset threshold range, and constructing a corresponding discrimination threshold curve according to the pulse measurement number corresponding to each of the multiple energy channel value distribution points corresponding to the count value of the neutron nuclear pulse signal and the preset threshold range. The discrimination threshold curve is also called a neutron pulse discrimination threshold curve.

[0071] After obtaining the discrimination threshold curve, the discrimination threshold curve is processed using a digital signal processing algorithm; the digital signal processing algorithm mainly includes discrimination threshold curve differential processing, Gaussian filtering processing and curve extreme value processing. Specifically, the obtained discrimination threshold curve is subjected to the discrimination threshold curve differential processing, Gaussian filtering processing and curve extreme value processing smoothing processing operations in sequence, and the measured neutron nuclear pulse signal energy spectrum is analyzed based on the discrimination threshold curve after smoothing processing, and the discrimination threshold is reversely adjusted based on the analysis result to realize automatic identification and adjustment of the discrimination threshold; the sensitivity and accuracy of the neutron detector of the delayed neutron monitoring system are improved.

[0072] S400, identifying the neutron spectrum change and delayed neutron precursor nuclides for the fuel element damage monitoring according to the discrimination threshold, the few-channel spectrum decomposition algorithm and the spectrum peak search algorithm, including:

[0073] According to the discrimination threshold and the few-channel spectrum analysis algorithm, the delayed neutron spectrum for monitoring the damage of the fuel element is obtained; the few-channel spectrum analysis algorithm includes: training of a neural network model. According to the delayed neutron spectrum and the spectrum peak search algorithm, the neutron spectrum change and the delayed neutron precursor nuclides for monitoring the damage of the fuel element are identified.

[0074] In the embodiment of the present application, the output pulse height of the neutron detector is divided into several parts according to the adjusted discrimination threshold, and the neutron nuclear pulse signal is counted again. The delayed neutron energy spectrum is solved by using a few-channel spectrum analysis algorithm, which is a generalized regression neural network (GRNN) program.

[0075] To solve the delayed neutron spectrum using the few-pass spectrum algorithm, it is necessary to integrate various types of neutron spectrum databases to train the neural network model so that the neural network model can automatically learn the characteristic relationship and constraints between the delayed neutron spectrum and the detector count based on the samples. The detector count is the count of the neutron nuclear pulse signal.

[0076] After multiple trainings, the neural network model will gradually converge stably. The actual measured counts of multiple detectors will be input into the input end of the neural network model in sequence. The neural network model will output the neutron flux in each energy interval in sequence, that is, a relatively smooth delayed neutron energy spectrum of a single partition will be obtained.

[0077] In the embodiment of the present application, the energy spectrum peak finding algorithm includes energy spectrum smoothing, morphological white hat transformation, false peak filtering and peak position calculation. The delayed neutron energy spectra of the measured m partitions are integrated by the energy spectrum peak finding algorithm to obtain the delayed neutron energy spectrum data around the reactor delayed neutron monitoring station.

[0078] Among them, energy spectrum smoothing is used to smooth the original energy spectrum, i.e., the delayed neutron energy spectrum of the present application, and filter out the high-frequency noise in the delayed neutron energy spectrum; the morphological white hat transformation is used to eliminate the background in the delayed neutron energy spectrum, extract the outline of the nuclide peak, and then filter out the false peaks through false peak filtering, retain the real nuclide peaks, and calculate the peak position information therefrom through peak position calculation.

[0079] Through real-time measurement of delayed neutron spectrum data and spectrum peak search, the neutron spectrum in the background environment and the changes in the neutron spectrum when the effective fuel element is damaged can be accurately compared. The delayed neutron precursor nuclides in the case of fuel element damage can be identified by using the spectrum peak search algorithm.

[0080] Taking the delayed neutron spectrum of a fast reactor as an example, the distribution of delayed neutron spectrum with and without fuel damage is as follows: Figure 2 The distribution of delayed neutron energy spectrum can reveal the change of neutron energy spectrum.

[0081] In the present application, the fuel element damage monitoring method based on delayed neutron spectrum measurement obtains the delayed neutron partition for fuel element damage monitoring; according to the delayed neutron partition and the delayed neutron partition multi-column spectrum measurement principle, the moderator for the fuel element damage monitoring is obtained; according to the moderator and the automatic identification algorithm of the discrimination threshold, the discrimination threshold for the fuel element damage monitoring is determined; according to the discrimination threshold, the few-channel spectrum analysis algorithm and the spectrum peak search algorithm, the neutron spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified. The present application analyzes and grasps the release mechanism of fission products under the damage of fast reactor fuel cladding, and proposes a fuel element damage monitoring method based on delayed neutron spectrum measurement, so as to judge the effective delayed neutron signal when a small break occurs in the fuel element. The present application adopts the automatic identification algorithm of the discrimination threshold to realize the online real-time measurement of the delayed neutron spectrum, realizes the online monitoring of fast reactor fuel element damage, and improves the speed and timeliness of fuel damage monitoring. The present application uses the Shaodao spectrum analysis algorithm to solve the delayed neutron spectrum in real time. The energy spectrum peak search algorithm is used to analyze the changes in the delayed neutron energy region in the energy spectrum and identify the elements at different peak positions. The changes in the neutron spectrum can be determined. When the delayed neutron precursor nuclides are identified by the energy spectrum peak search algorithm, it is determined that effective fuel element damage has occurred. The method described in the present application can theoretically reduce the minimum damage area of ​​the monitored fuel to 1cm 2 or less, which solves the problem that the delayed neutron injection rate at the neutron detector must be increased to more than Only then can the defects with effective delayed neutron signals be measured from the background.

[0082] The following are embodiments of the apparatus of the present invention, which can be used to implement the embodiments of the method of the present invention. For details not disclosed in the embodiments of the apparatus of the present invention, please refer to the embodiments of the method of the present invention.

[0083] See also Figure 3 , which shows a schematic structural diagram of a fuel element damage monitoring device based on delayed neutron spectrum measurement provided by an exemplary embodiment of the present invention. The device includes: an acquisition module 10000, a moderator determination module 20000, a discrimination threshold determination module 30000 and an identification module 40000.

[0084] An acquisition module 10000 is used to acquire delayed neutron partitions for fuel element damage monitoring;

[0085] A moderator determination module 20000 is used to obtain the moderator for the fuel element damage monitoring according to the delayed neutron partition and the delayed neutron partition multi-column spectrum measurement principle;

[0086] A discrimination threshold determination module 30000 is used to determine the discrimination threshold for monitoring the damage of the fuel element according to the moderator and the discrimination threshold automatic identification algorithm;

[0087] The identification module 40000 is used to identify the neutron spectrum changes and delayed neutron precursor nuclides for the fuel element damage monitoring according to the discrimination threshold, the few-channel spectrum analysis algorithm and the energy spectrum peak search algorithm.

[0088] According to a preferred embodiment, the discrimination threshold determination module 30000 is specifically used for:

[0089] An analysis unit, configured to obtain a neutron energy response function of the detector for monitoring damage of the fuel element according to the moderator and modeling simulation analysis;

[0090] A determination unit is used to determine the discrimination threshold for monitoring the damage of the fuel element according to the neutron energy response function of the detector and the automatic discrimination threshold recognition algorithm.

[0091] According to a preferred embodiment, the determining unit is specifically configured to:

[0092] According to the detector neutron energy response function and the threshold time-sharing automatic scanning method for generating a discrimination threshold curve, constructing the discrimination threshold curve for monitoring the damage of the fuel element;

[0093] Determining a discrimination threshold for monitoring damage of the fuel element according to the discrimination threshold curve and the digital signal processing algorithm;

[0094] The method of automatically scanning the threshold value in time-sharing to generate a discrimination threshold curve and the digital signal processing algorithm are used as the automatic discrimination threshold recognition algorithm.

[0095] According to a preferred embodiment, the identification module 40000 is specifically used for:

[0096] Obtaining a delayed neutron energy spectrum for monitoring damage of the fuel element according to the discrimination threshold and the few-channel spectrum analysis algorithm;

[0097] According to the delayed neutron energy spectrum and the energy spectrum peak-finding algorithm, the neutron energy spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified.

[0098] According to a preferred embodiment, it is characterized in that the few-channel spectral analysis algorithm includes: training of a neural network model.

[0099] It should be noted that the fuel element damage monitoring device based on delayed neutron spectrum measurement provided in the above embodiment only uses the division of the above functional modules as an example when executing the fuel element damage monitoring method based on delayed neutron spectrum measurement. In actual applications, the above functions can be assigned to different functional modules as needed, that is, the internal structure of the device can be divided into different functional modules to complete all or part of the functions described above. In addition, the fuel element damage monitoring device based on delayed neutron spectrum measurement provided in the above embodiment and the fuel element damage monitoring method based on delayed neutron spectrum measurement belong to the same concept. The implementation process is detailed in the method embodiment, which will not be repeated here.

[0100] In the present application, the fuel element damage monitoring device based on delayed neutron spectrum measurement obtains delayed neutron partitions for fuel element damage monitoring; obtains the moderator for fuel element damage monitoring according to the delayed neutron partitions and delayed neutron partition multi-column spectrum measurement principle; determines the discrimination threshold for fuel element damage monitoring according to the moderator and the discrimination threshold automatic identification algorithm; identifies the neutron spectrum changes and delayed neutron precursor nuclides for fuel element damage monitoring according to the discrimination threshold, the few-channel spectrum analysis algorithm and the spectrum peak search algorithm. The present application adopts the discrimination threshold automatic identification algorithm to realize the online real-time measurement of delayed neutron spectrum, realizes the online monitoring of fast reactor fuel element damage, and improves the speed and timeliness of fuel damage monitoring. The present application uses the Shaodao spectrum analysis algorithm to solve the delayed neutron spectrum in real time. The energy spectrum peak search algorithm is used to analyze the changes in the delayed neutron energy region in the energy spectrum and identify the elements at different peak positions. The changes in the neutron spectrum can be determined. When the delayed neutron precursor nuclides are identified by the energy spectrum peak search algorithm, it is determined that effective fuel element damage has occurred. The method described in the present application can theoretically reduce the minimum damage area of ​​the monitored fuel to 1cm 2 or less, which solves the problem that the delayed neutron injection rate at the neutron detector must be increased to more than Only then can the defects with effective delayed neutron signals be measured from the background.

[0101] The present invention also provides a computer-readable medium having program instructions stored thereon, and when the program instructions are executed by a processor, the fuel element damage monitoring method based on delayed neutron spectrum measurement provided by the above-mentioned various method embodiments is implemented.

[0102] The present invention also provides a computer program product comprising instructions, which, when executed on a computer, enables the computer to execute the fuel element damage monitoring method based on delayed neutron spectrum measurement in the above-mentioned various method embodiments.

[0103] See also Figure 4 , which is a schematic diagram of the structure of a terminal according to an embodiment of the present application. The terminal may include: at least one processor 1001, at least one network interface 1004, a user interface 1003, a memory 1005, and at least one communication bus 1002.

[0104] The communication bus 1002 is used to realize the connection and communication between these components.

[0105] The user interface 1003 may include a display screen (Display) and a camera (Camera), and the optional user interface 1003 may also include a standard wired interface and a wireless interface.

[0106] The network interface 1004 may optionally include a standard wired interface or a wireless interface (such as a WI-FI interface).

[0107] Among them, the processor 1001 may include one or more processing cores. The processor 1001 uses various interfaces and lines to connect various parts in the entire terminal, and executes various functions of the terminal and processes data by running or executing instructions, programs, code sets or instruction sets stored in the memory 1005, and calling data stored in the memory 1005. Optionally, the processor 1001 can be implemented in at least one hardware form of digital signal processing (Digital Signal Processing, DSP), field programmable gate array (Field-Programmable Gate Array, FPGA), and programmable logic array (Programmable Logic Array, PLA). The processor 1001 can integrate one or a combination of a central processing unit (Central Processing Unit, CPU), a graphics processing unit (Graphics Processing Unit, GPU) and a modem. Among them, the CPU mainly processes the operating system, user interface and application programs; the GPU is responsible for rendering and drawing the content to be displayed on the display screen; the modem is used to process wireless communications. It can be understood that the above-mentioned modem may not be integrated into the processor 1001, and it can be implemented separately through a chip.

[0108] Among them, the memory 1005 may include a random access memory (Random Access Memory, RAM) and may also include a read-only memory (Read-Only Memory). Optionally, the memory 1005 includes a non-transitory computer-readable storage medium. The memory 1005 can be used to store instructions, programs, codes, code sets or instruction sets. The memory 1005 may include a program storage area and a data storage area, wherein the program storage area may store instructions for implementing an operating system, instructions for at least one function (such as a touch function, a sound playback function, an image playback function, etc.), instructions for implementing the above-mentioned various method embodiments, etc.; the data storage area may store data involved in the above-mentioned various method embodiments, etc. The memory 1005 may optionally be at least one storage device located away from the aforementioned processor 1001. As Figure 4 As shown, the memory 1005 as a computer storage medium may include an operating system, a network communication module, a user interface module, and a fuel element damage monitoring application based on delayed neutron spectrum measurement.

[0109] exist Figure 4In the terminal shown, the user interface 1003 is mainly used to provide an input interface for the user and obtain the data input by the user; and the processor 1001 can be used to call the fuel element damage monitoring application based on delayed neutron spectrum measurement stored in the memory 1005, and specifically perform the following operations:

[0110] Obtaining delayed neutron partitions for fuel element damage monitoring;

[0111] According to the delayed neutron partition and delayed neutron partition multi-column spectrum measurement principle, a moderator for monitoring the damage of the fuel element is obtained;

[0112] Determining the discrimination threshold for monitoring damage of the fuel element according to the moderator and discrimination threshold automatic identification algorithm;

[0113] According to the discrimination threshold, the few-channel spectrum analysis algorithm and the spectrum peak search algorithm, the neutron spectrum changes and delayed neutron precursor nuclides for the fuel element damage monitoring are identified; wherein the few-channel spectrum analysis algorithm includes: training of a neural network model.

[0114] In one embodiment, when the processor 1001 executes the automatic identification algorithm according to the moderator and the discrimination threshold to determine the discrimination threshold for monitoring the damage of the fuel element, the processor 1001 specifically performs the following operations:

[0115] According to the moderator and modeling simulation analysis, a neutron energy response function of the detector for monitoring the damage of the fuel element is obtained;

[0116] The discrimination threshold for monitoring the damage of the fuel element is determined according to the neutron energy response function of the detector and the automatic discrimination threshold identification algorithm.

[0117] In one embodiment, when the processor 1001 executes the automatic identification algorithm for determining the discrimination threshold for monitoring the damage of the fuel element according to the neutron energy response function of the detector and the discrimination threshold, the processor 1001 specifically performs the following operations:

[0118] According to the detector neutron energy response function and the threshold time-sharing automatic scanning method for generating a discrimination threshold curve, constructing the discrimination threshold curve for monitoring the damage of the fuel element;

[0119] Determining a discrimination threshold for monitoring damage of the fuel element according to the discrimination threshold curve and the digital signal processing algorithm;

[0120] The method of automatically scanning the threshold value in time-sharing to generate a discrimination threshold curve and the digital signal processing algorithm are used as the automatic discrimination threshold recognition algorithm.

[0121] In one embodiment, when the processor 1001 executes the identification of the neutron spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring according to the discrimination threshold, the few-channel spectrum decomposition algorithm and the energy spectrum peak search algorithm, the processor 1001 specifically performs the following operations:

[0122] Obtaining a delayed neutron energy spectrum for monitoring damage of the fuel element according to the discrimination threshold and the few-channel spectrum analysis algorithm;

[0123] According to the delayed neutron energy spectrum and the energy spectrum peak-finding algorithm, the neutron energy spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified.

[0124] In the present application, the method and device for monitoring fuel element damage based on delayed neutron spectrum measurement obtains delayed neutron partitions for monitoring fuel element damage; obtains the moderator for monitoring fuel element damage based on the delayed neutron partitions and delayed neutron partition multi-column spectrum measurement principle; determines the discrimination threshold for monitoring fuel element damage based on the moderator and the discrimination threshold automatic identification algorithm; identifies the neutron spectrum changes and delayed neutron precursor nuclides for monitoring fuel element damage based on the discrimination threshold, the few-channel spectrum analysis algorithm and the spectrum peak search algorithm. The present application uses the discrimination threshold automatic identification algorithm to realize online real-time measurement of delayed neutron spectrum, realizes online monitoring of fast reactor fuel element damage, and improves the speed and timeliness of fuel damage monitoring. The present application uses the Shaodao spectrum analysis algorithm to solve the delayed neutron spectrum in real time. The energy spectrum peak search algorithm is used to analyze the changes in the delayed neutron energy region in the energy spectrum and identify the elements at different peak positions. The changes in the neutron spectrum can be determined. When the delayed neutron precursor nuclides are identified by the energy spectrum peak search algorithm, it is determined that effective fuel element damage has occurred. The method described in the present application can theoretically reduce the minimum damage area of ​​the monitored fuel to 1cm 2 or less, which solves the problem that the delayed neutron injection rate at the neutron detector must be increased to more than Only then can the defects with effective delayed neutron signals be measured from the background.

[0125] Those skilled in the art can understand that all or part of the processes in the above-mentioned embodiments can be implemented by instructing related hardware through a computer program, and the program can be stored in a computer-readable storage medium, and when the program is executed, it can include the processes of the embodiments of the above-mentioned methods. The storage medium can be a disk, an optical disk, a read-only storage memory, or a random access memory, etc.

[0126] The above disclosure is only the preferred embodiment of the present application, which certainly cannot be used to limit the scope of rights of the present application. Therefore, equivalent changes made according to the claims of the present application are still within the scope covered by the present application.

Claims

1. A fuel element damage monitoring method based on delayed neutron spectrum measurement, characterized in that: The following steps are involved: Obtaining delayed neutron partitions for fuel element damage monitoring; According to the delayed neutron partition and delayed neutron partition multi-column spectrum measurement principle, a moderator for monitoring the damage of the fuel element is obtained; Determining the discrimination threshold for monitoring damage of the fuel element according to the moderator and discrimination threshold automatic identification algorithm; According to the discrimination threshold, the few-channel spectrum analysis algorithm and the spectrum peak search algorithm, the neutron spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified.

2. The fuel element damage monitoring method based on delayed neutron spectrum measurement according to claim 1 is characterized in that: The step of determining the discrimination threshold for monitoring damage of the fuel element according to the moderator and the discrimination threshold automatic identification algorithm comprises: According to the moderator and modeling simulation analysis, a neutron energy response function of the detector for monitoring the damage of the fuel element is obtained; The discrimination threshold for monitoring the damage of the fuel element is determined according to the neutron energy response function of the detector and the automatic discrimination threshold identification algorithm.

3. The method for monitoring fuel element damage based on delayed neutron spectrum measurement according to claim 2, characterized in that: Determining the discrimination threshold for monitoring fuel element damage according to the detector neutron energy response function and the discrimination threshold automatic identification algorithm includes: According to the detector neutron energy response function and the threshold time-sharing automatic scanning method for generating a discrimination threshold curve, constructing the discrimination threshold curve for monitoring the damage of the fuel element; Determining a discrimination threshold for monitoring damage of the fuel element according to the discrimination threshold curve and the digital signal processing algorithm; The method of automatically scanning the threshold value in time-sharing to generate a discrimination threshold curve and the digital signal processing algorithm are used as the automatic discrimination threshold recognition algorithm.

4. The fuel element damage monitoring method based on delayed neutron spectrum measurement according to claim 1 is characterized in that: The method of identifying the neutron spectrum change and delayed neutron precursor nuclides for monitoring the damage of the fuel element according to the discrimination threshold, the few-channel spectrum analysis algorithm and the spectrum peak search algorithm includes: Obtaining a delayed neutron energy spectrum for monitoring damage of the fuel element according to the discrimination threshold and the few-channel spectrum analysis algorithm; According to the delayed neutron energy spectrum and the energy spectrum peak-finding algorithm, the neutron energy spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified.

5. The method for monitoring fuel element damage based on delayed neutron spectrum measurement according to claim 1, characterized in that: The few-channel spectrum analysis algorithm includes: training of a neural network model.

6. A fuel element damage monitoring device based on delayed neutron spectrum measurement, the device is used to execute the fuel element damage monitoring method based on delayed neutron spectrum measurement according to any one of claims 1 to 5, characterized in that: include: An acquisition module, used to acquire delayed neutron partitions for fuel element damage monitoring; A moderator determination module, used for obtaining the moderator for monitoring the damage of the fuel element according to the delayed neutron partition and the delayed neutron partition multi-column spectrum measurement principle; A discrimination threshold determination module, used to determine the discrimination threshold for monitoring the damage of the fuel element according to the moderator and the discrimination threshold automatic identification algorithm; The identification module is used to identify the neutron spectrum changes and delayed neutron precursor nuclides for the fuel element damage monitoring according to the discrimination threshold, the few-channel spectrum analysis algorithm and the energy spectrum peak search algorithm.

7. The fuel element damage monitoring device based on delayed neutron spectrum measurement according to claim 6 is characterized in that: The discrimination threshold determination module is specifically used for: An analysis unit, configured to obtain a neutron energy response function of the detector for monitoring damage of the fuel element according to the moderator and modeling simulation analysis; A determination unit is used to determine the discrimination threshold for monitoring the damage of the fuel element according to the neutron energy response function of the detector and the automatic discrimination threshold recognition algorithm.

8. The fuel element damage monitoring device based on delayed neutron spectrum measurement according to claim 7 is characterized in that: The determining unit is specifically configured to: According to the detector neutron energy response function and the threshold time-sharing automatic scanning method for generating a discrimination threshold curve, constructing the discrimination threshold curve for monitoring the damage of the fuel element; Determining a discrimination threshold for monitoring damage of the fuel element according to the discrimination threshold curve and the digital signal processing algorithm; The method of automatically scanning the threshold value in time-sharing to generate a discrimination threshold curve and the digital signal processing algorithm are used as the discrimination threshold automatic identification algorithm.

9. The fuel element damage monitoring device based on delayed neutron spectrum measurement according to claim 6, characterized in that: The identification module is specifically used for: Obtaining a delayed neutron energy spectrum for monitoring damage of the fuel element according to the discrimination threshold and the few-channel spectrum analysis algorithm; According to the delayed neutron energy spectrum and the energy spectrum peak-finding algorithm, the neutron energy spectrum change and the delayed neutron precursor nuclides for the fuel element damage monitoring are identified.

10. The fuel element damage monitoring device based on delayed neutron spectrum measurement according to claim 6, characterized in that: The few-channel spectrum analysis algorithm includes: training of a neural network model.

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