Method for distinguishing high and low enrichment degree fuel elements of high-temperature gas cooled reactor and related device

Abstract

The embodiment of the invention relates to a high-temperature gas cooled reactor high-low enrichment fuel element distinguishing method and a related device, and the method comprises the following steps: sending a fuel consumption result request of a fuel element in a reactor core at a reactor shutdown moment to reactor physical analysis software, and receiving a fuel consumption result of the fuel element in the reactor core returned by the reactor physical analysis software, the decay amount of characteristic nuclides of the fuel elements in the discharge pipe is determined based on the shutdown time, the sorting limit value of the characteristic nuclides is determined according to the reactor state parameters before shutdown, the burnup result and the decay amount, and the sorting result of the fuel elements to be sorted is determined based on the sorting limit value so as to distinguish the high enrichment degree and the low enrichment degree of the fuel elements to be sorted. By adopting the technical scheme, the high enrichment degree and the low enrichment degree of the to-be-sorted fuel element can be correctly distinguished within a long time after the high-temperature gas cooled reactor is shut down and restarted for a long time, the precision and the reliability of a measurement result are effectively improved, and the burn-up state of the to-be-sorted fuel element can be more comprehensively reflected.

Description

TECHNICAL FIELD

[0001] The present disclosure relates to the field of high temperature gas cooled reactor burnup measurement, in particular to a method for distinguishing high and low enrichment fuel elements of a high temperature gas cooled reactor and related device. BACKGROUND

[0002] With the increasing requirements of fuel element sorting reliability and reactor core operation stability of nuclear power plants, the online burnup measurement technology of the high temperature gas cooled reactor is particularly important.

[0003] During the operation of the high temperature gas cooled reactor, if the reactor is shut down for a long time, the system cannot correctly distinguish the high and low enrichment fuel elements for a long time after the reactor is restarted. SUMMARY

[0004] To solve the above technical problems, the present disclosure provides a method for distinguishing high and low enrichment fuel elements of a high temperature gas cooled reactor and related device.

[0005] The present disclosure provides a method for distinguishing high and low enrichment fuel elements of a high temperature gas cooled reactor, which comprises: sending a burnup result request of fuel elements in a reactor core at a shutdown time to a reactor physics analysis software, wherein the burnup result request carries input information required by the reactor physics analysis software; receiving a burnup result of the fuel elements in the reactor core returned by the reactor physics analysis software, wherein the burnup result includes activity values of characteristic nuclides of the fuel elements in the reactor core; determining a decay amount of the characteristic nuclides of the fuel elements in a discharge pipe based on a shutdown time; determining a sorting limit value of the characteristic nuclides according to a reactor state parameter before shutdown, the burnup result and the decay amount; determining a sorting result of the fuel elements to be sorted based on the sorting limit value, so as to distinguish high and low enrichment of the fuel elements to be sorted.

[0006] The present disclosure also provides a device for distinguishing high and low enrichment fuel elements of a high temperature gas cooled reactor, which comprises: a sending module configured to send a burnup result request of fuel elements in a reactor core at a shutdown time to a reactor physics analysis software, wherein the burnup result request carries input information required by the reactor physics analysis software; a receiving module configured to receive a burnup result of the fuel elements in the reactor core returned by the reactor physics analysis software, wherein the burnup result includes activity values of characteristic nuclides of the fuel elements in the reactor core; a first determining module configured to determine a decay amount of the characteristic nuclides of the fuel elements in a discharge pipe based on a shutdown time; The second determining module is configured to determine a sorting limit value of the characteristic nuclide according to the reactor state parameter before shutdown, the burnup result, and the decay amount. The third determining module is configured to determine a sorting result of the fuel element to be sorted based on the sorting limit value, so as to distinguish high and low enrichment degrees of the fuel element to be sorted.

[0007] The electronic device includes a processor, a memory for storing executable instructions of the processor, and the processor is configured to read the executable instructions from the memory and execute the executable instructions to implement the method for distinguishing high and low enrichment degrees of the fuel element of the high-temperature gas-cooled reactor.

[0008] The electronic device includes a processor, a memory for storing executable instructions of the processor, and the processor is configured to read the executable instructions from the memory and execute the executable instructions to implement the method for distinguishing high and low enrichment degrees of the fuel element of the high-temperature gas-cooled reactor.

[0009] The electronic device includes a processor, a memory for storing executable instructions of the processor, and the processor is configured to read the executable instructions from the memory and execute the executable instructions to implement the method for distinguishing high and low enrichment degrees of the fuel element of the high-temperature gas-cooled reactor.

[0010] The electronic device includes a processor, a memory for storing executable instructions of the processor, and the processor is configured to read the executable instructions from the memory and execute the executable instructions to implement the method for distinguishing high and low enrichment degrees of the fuel element of the high-temperature gas-cooled reactor. BRIEF DESCRIPTION OF DRAWINGS

[0011] The above and other features, advantages, and aspects of the embodiments of the present disclosure will become more apparent with reference to the following detailed description in conjunction with the accompanying drawings. Throughout the drawings, the same or similar reference numerals denote the same or similar elements. It should be understood that the drawings are schematic, and the original and elements are not necessarily drawn according to the scale. The above and other features, advantages, and aspects of the embodiments of the present disclosure will become more apparent with reference to the following detailed description in conjunction with the accompanying drawings. Throughout the drawings, the same or similar reference numerals denote the same or similar elements. It should be understood that the drawings are schematic, and the original and elements are not necessarily drawn according to the scale.

[0012] Figure 1 A flowchart of a high-low enrichment fuel element distinguishing method of a high-temperature gas-cooled reactor according to an embodiment of the present disclosure is shown in FIG. 1. Figure 2 A structural diagram of a high-low enrichment fuel element distinguishing device of a high-temperature gas-cooled reactor according to an embodiment of the present disclosure is shown in FIG. 2. Figure 3 A structural diagram of an electronic device according to an embodiment of the present disclosure is shown in FIG. 3. DETAILED DESCRIPTION

[0013] Embodiments of the present disclosure will be described in more detail with reference to the accompanying drawings. While certain embodiments of the present disclosure are shown in the drawings, it is understood that the present disclosure can be embodied in various forms and should not be interpreted as being limited to the embodiments set forth herein; rather, these embodiments are provided so that the present disclosure can be more thoroughly and completely understood. It should be understood that the drawings of the present disclosure are for illustrative purposes only and are not intended to limit the scope of the present disclosure.

[0014] It should be understood that each of the steps recited in the method embodiments of the present disclosure can be executed in different orders and / or in parallel. In addition, the method embodiments can include additional steps and / or omit the execution of the steps shown. The scope of the present disclosure is not limited in this respect.

[0015] The term “comprising” and variations thereof as used in the present disclosure are open-ended, that is, “including but not limited to”. The term “based on” is “based, at least in part, on”. The term “one embodiment” means “at least one embodiment”; the term “another embodiment” means “at least one additional embodiment”; the term “some embodiments” means “at least some embodiments”. Related definitions are given throughout the description.

[0016] It should be noted that the concepts of “first”, “second”, etc. mentioned in the present disclosure are only used to distinguish different devices, modules or units, and are not intended to limit the order or interdependence of the functions performed by these devices, modules or units.

[0017] It should be noted that the modification of “one”, “multiple” mentioned in the present disclosure is illustrative and not limiting, and those skilled in the art should understand that, unless otherwise explicitly indicated in the context, it should be understood as “one or more”.

[0018] The names of the messages or information exchanged between the multiple devices in the embodiments of the present disclosure are only for illustrative purposes, and are not intended to limit the scope of the messages or information.

[0020] With the operation of HTR-PM demonstration project, the pebble bed high temperature gas cooled reactor online non-destructive burnup measurement system encounters great challenges, and there are many problems in the reliability of the equipment, the sorting of high and low enrichment fuel balls, and the measurement accuracy, which puts forward urgent demand for further improvement of online non-destructive burnup measurement technology, so from the aspect of improving the reliability of the field system or from the aspect of the development requirement of high temperature reactor technology, the online non-destructive burnup measurement technology research of pebble bed high temperature gas cooled reactor has extremely important significance.

[0021] The present application is mainly aimed at the problem that if the reactor is stopped for a long time, the system cannot correctly distinguish the high and low enrichment fuel elements for a long time after the reactor is started again.

[0022] In order to solve the above problems, the embodiment of the present disclosure provides a high and low enrichment fuel element distinguishing method for a high temperature gas cooled reactor, which will be introduced below in combination with specific embodiments.

[0023] Figure 1 A flowchart of the high and low enrichment fuel element distinguishing method for a high temperature gas cooled reactor provided by the embodiment of the present disclosure, which can be executed by a high and low enrichment fuel element distinguishing device for a high temperature gas cooled reactor, wherein the device can be realized by software and / or hardware, and can be generally integrated in an electronic device. As shown in the figure, the method comprises: Figure 1 S101, sending a burnup result request of fuel elements in the core at the shutdown time to a reactor physics analysis software; wherein the burnup result request carries the input information required by the reactor physics analysis software.

[0024] The high and low enrichment fuel element distinguishing method for a high temperature gas cooled reactor provided by the embodiment of the present disclosure is applied to a burnup measurement system software.

[0025] The reactor physics analysis software refers to the software for calculating the burnup of fuel elements in the core. The fuel element is the core component of the nuclear reactor which loads nuclear fuel, realizes nuclear fission reaction and releases energy, and its core function is to wrap nuclear fuel, maintain nuclear reaction conditions and prevent leakage of radioactive substances, and it is the basic carrier of energy output of the reactor, such as fuel ball. The burnup result request refers to the request initiated by the burnup measurement system software to the reactor physics analysis software for obtaining the burnup degree of the fuel elements in the core under a specific working condition (such as the shutdown time). The input information includes the core power and the operation time of the high temperature gas cooled reactor.

[0026] ​In this embodiment of the disclosure, reactor physics analysis software is used to calculate the fuel element burnup in the reactor core. Specifically, an interface is established between the reactor physics analysis software and the burnup measurement system software. When the reactor is shut down and restarted, the burnup measurement system software sends a request to the reactor physics analysis software for the fuel element burnup results in the reactor core. The request carries the input information required by the reactor physics analysis software. The results are saved after they are received.

[0027] In this embodiment of the disclosure, since the burnup result request carries the input information required by the reactor physics analysis software, such as the core power and the operating time of the high-temperature gas-cooled reactor, the burnup result of the fuel elements in the core determined by the reactor physics analysis software is more accurate when the core power changes dynamically.

[0028] S102. Receive the burnup results of the fuel elements in the reactor core returned by the reactor physics analysis software; wherein the burnup results include the activity values ​​of the characteristic nuclides of the fuel elements in the reactor core.

[0029] Here, burnup result refers to a quantitative description of the degree of nuclear fuel consumption in the fuel element. Characteristic nuclide refers to a nuclide that reflects the enrichment level of the fuel element. The characteristic nuclides required in the embodiments of this disclosure include, but are not limited to, those mentioned above. 95 Zr、 242 Cm、 233 Pa、 103 Ru、 148 mPm. Activity value is a physical quantity (unit: Bq, becquerel) used to quantify the radioactivity of a characteristic nuclide. It represents the number of atomic nuclei that decay per unit time and is a key quantitative basis for subsequent calculation of sorting limits and differentiation of fuel element enrichment.

[0030] In this embodiment of the disclosure, the burnup measurement system software receives the burnup results of the fuel elements in the reactor core returned by the software reactor physics analysis software. The burnup results include the activity values ​​of the characteristic nuclides of the fuel elements in the reactor core, providing core data support for subsequent determination of the enrichment degree of the fuel elements and determination of sorting limits.

[0031] S103. Determine the decay variables of characteristic nuclides in the fuel element within the unloading pipe based on the reactor shutdown time.

[0032] The fuel elements in the unloading pipe can be from the same batch as the fuel elements in the reactor core. Decay refers to the total reduction in activity of a characteristic nuclide in the fuel elements in the unloading pipe due to radioactive decay during a specific period of reactor shutdown. It is the difference between the initial activity value of the characteristic nuclide at the time of shutdown and the remaining activity value after decay over the shutdown period, reflecting the degree of reduction in radioactivity intensity caused by natural decay during shutdown.

[0033] In this embodiment of the disclosure, since the fuel elements below the unloading pipe mainly decay after the reactor is shut down, the decay variables of the characteristic nuclides are calculated to obtain the decay variables of the characteristic nuclides. Specifically, the decay variables of the characteristic nuclides of the fuel elements in the unloading pipe are calculated based on the shutdown time.

[0034] In this embodiment of the present disclosure, the initial activity value of the characteristic nuclide of the fuel element in the unloading pipe at the time of reactor shutdown is first determined. Based on the half-life characteristics of the characteristic nuclide, the activity decay ratio of the characteristic nuclide during the shutdown time is queried and calculated through a preset nuclide decay characteristic database. The remaining activity value is calculated according to the decay ratio. The decay value of the characteristic nuclide of the fuel element in the unloading pipe is obtained by subtracting the initial activity value from the remaining activity value.

[0035] S104. Based on the reactor state parameters, burnup results, and decay variables before shutdown, determine the sorting limits for characteristic nuclides.

[0036] The reactor status parameters before shutdown include refueling ratio, refueling rate, and core power. The refueling phase is used to characterize the refueling ratio of fuel elements with different enrichment levels.

[0037] The sorting limit for characteristic nuclides refers to the benchmark value for determining the activity of characteristic nuclides in the high-temperature gas-cooled reactor (HTGR) fuel element sorting scenario. This value is determined by combining reactor state parameters before shutdown, burnup results output by reactor physics analysis software, and decay variables of characteristic nuclides calculated based on shutdown time. This sorting limit is compared with the activity values ​​of characteristic nuclides in the fuel elements to be sorted measured by a spectrometer. It serves as the core basis for distinguishing between high and low enrichment levels in the fuel elements to be sorted, ensuring accurate determination of high and low enrichment levels even after a prolonged shutdown and restart of the HTGR.

[0038] In this embodiment of the disclosure, since the high and low enrichment degree sorting limit of the reactor cannot be analyzed according to the sorting limit when it is running at full power under special operating conditions, such as after the reactor is shut down for a period of time and then restarted, it is necessary to calculate a new sorting limit in real time. This value is obtained by comprehensive calculation and analysis based on the reactor state parameters before shutdown, fission status (i.e. combustion results), and decay status (i.e. decay amount).

[0039] In one optional implementation, the sorting limit of the characteristic nuclide is determined based on the reactor state parameters before shutdown, burnup results, and decay variables. This includes: using VSOP to calculate the reactor state parameters before shutdown and the burnup results to obtain the initial sorting limit of the characteristic nuclide; dynamically correcting the initial sorting limit based on the decay variables to obtain the corrected sorting limit; and using the corrected sorting limit as the sorting limit of the characteristic nuclide.

[0040] VSOP, also known as Very Superior Old Program, is a comprehensive simulation program system in the field of nuclear reactors used for core physics analysis, fuel burnup calculation, and fuel management schemes.

[0041] In this embodiment of the disclosure, after obtaining the initial sorting limit of the characteristic nuclide, the initial sorting limit is used as a basis to subtract the decay variable to complete the correction, and the corrected sorting limit is obtained. Finally, the corrected sorting limit is determined as the sorting limit of the characteristic nuclide and is used as the basis for subsequent determination of high and low enrichment of fuel elements.

[0042] In one optional implementation, the characteristic nuclides include multiple types. Based on reactor state parameters before shutdown, burnup results, and decay variables, sorting limits for the characteristic nuclides are determined, including: determining the sorting limit for each characteristic nuclide based on the reactor state parameters before shutdown, burnup results, and decay variables; correspondingly, based on the sorting limits, the sorting result for the fuel elements to be sorted is determined, including: determining the sorting result for the fuel elements to be sorted based on the sorting limits for each characteristic nuclide and the confidence level of each characteristic nuclide.

[0043] In this embodiment of the disclosure, the multiple characteristic nuclides can be multiple characteristic nuclides with different fission yields, half-lives, and neutron reaction cross sections. The method for determining the sorting limits of each characteristic nuclide is as described above.

[0044] In this embodiment of the disclosure, firstly, for multiple characteristic nuclides, the activity sorting limit value of each characteristic nuclide is determined. For the fuel element to be sorted, the measured activity values ​​of each characteristic nuclide of the fuel element to be sorted are received from the spectrometer, and each value is compared with the sorting limit value of the corresponding characteristic nuclide to obtain the judgment result of each characteristic nuclide. Then, the judgment results are weighted according to the confidence level of each characteristic nuclide to determine the sorting result of the fuel element to be sorted.

[0045] The confidence level of each characteristic nuclide is determined based on the half-life of the corresponding characteristic nuclide, the activity value of the corresponding characteristic nuclide, and the shutdown time.

[0046] The activity value of the characteristic nuclide can be the activity value of the characteristic nuclide in the fuel element being tested at the current measurement time.

[0047] In this embodiment of the disclosure, a confidence weight is assigned to each characteristic nuclide based on the shutdown time, the half-life of each characteristic nuclide, and the activity value of each characteristic nuclide. Since this method uses multiple characteristic nuclides to jointly determine whether a fuel element is highly enriched or lowly enriched, the confidence of a characteristic nuclide as a sorting characteristic nuclide is obtained by comprehensively considering factors such as its half-life, activity value, and shutdown time.

[0048] In this embodiment of the disclosure, taking the target characteristic nuclide as an example, firstly, the half-life of the target characteristic nuclide is compared with the half-life of a preset reference nuclide in the reactor to obtain a half-life score; then, the activity value of the target characteristic nuclide is compared with the maximum activity of a preset reference nuclide in the reactor to obtain an activity score; next, the proportion of the reactor shutdown time to the reference time is calculated based on the duration corresponding to 10 half-lives of the target characteristic nuclide, and the time score is obtained by subtracting the proportion from 1; finally, the three scores are weighted and summed according to the preset weights of the half-life score, activity score, and time score, and the result is the confidence level of the target characteristic nuclide.

[0049] S105. Based on the sorting limit, determine the sorting result of the fuel element to be sorted, so as to distinguish between high and low enrichment of the fuel element to be sorted.

[0050] Among them, fuel elements to be sorted refer to fuel elements that need to be distinguished between high and low enrichment.

[0051] In this embodiment of the disclosure, after determining the sorting limit of the characteristic nuclide, the sorting limit of the characteristic nuclide is updated to the fuel consumption measurement system in real time, and the sorting result of the fuel element is obtained by calculation using the sorting limit of the characteristic nuclide.

[0052] In one optional implementation, determining the sorting result of the fuel element to be sorted based on the sorting limit includes: determining the sorting result of the fuel element to be sorted based on the sorting limit and the activity value of the characteristic nuclide of the fuel element to be sorted sent by the spectrometer.

[0053] The activity values ​​of the characteristic nuclides of the fuel element transmitted by the spectrometer refer to the activity values ​​of the characteristic nuclides of the fuel element to be sorted, which are actually measured by the spectrometer.

[0054] In this embodiment of the disclosure, when the characteristic nuclide is a single element, the activity value of the characteristic nuclide of the fuel element to be sorted is obtained by a spectrometer. The activity value of the characteristic nuclide of the fuel element to be sorted is compared with the sorting limit. If the activity value of the characteristic nuclide of the fuel element to be sorted is greater than the sorting limit, the fuel element to be sorted is determined to be a high-enrichment fuel element. If the activity value of the characteristic nuclide of the fuel element to be sorted is less than the sorting limit, the fuel element to be sorted is determined to be a low-enrichment fuel element.

[0055] The high- and low enrichment fuel element differentiation scheme for high-temperature gas-cooled reactors provided in this disclosure sends a request for burnup results of fuel elements in the reactor core at the time of reactor shutdown to reactor physics analysis software. The burnup result request carries the input information required by the reactor physics analysis software and receives the burnup results of fuel elements in the reactor core returned by the software. The burnup results include the activity values ​​of characteristic nuclides of the fuel elements in the reactor core. Based on the shutdown time, the decay variables of characteristic nuclides in the unloading pipe are determined. Based on the reactor state parameters before shutdown, the burnup results, and the decay variables, sorting limits for the characteristic nuclides are determined. Based on the sorting limits, the sorting results of the fuel elements to be sorted are determined to differentiate between high and low enrichment. Using this technical solution, the high- and low enrichment of fuel elements to be sorted can be correctly differentiated over a long period after a prolonged shutdown and restart of the high-temperature gas-cooled reactor, effectively improving the accuracy and reliability of the measurement results and providing a more comprehensive reflection of the burnup status of the fuel elements to be sorted.

[0056] This disclosure proposes a multi-nucleoside joint verification analysis method. By selecting multiple characteristic nuclides with different fission yields, half-lives, and neutron reaction cross sections, this method can establish a more accurate burnup calculation model, improve the accuracy and reliability of measurement results, and more comprehensively reflect the burnup status of the fuel sphere.

[0057] Figure 2 This is a schematic diagram of a high- and low-enrichment fuel element differentiation device for a high-temperature gas-cooled reactor, provided in an embodiment of this disclosure. This device can be implemented by software and / or hardware, and is generally integrated into electronic equipment. Figure 2 As shown, it includes: The sending module 201 is used to send a request for the burnup results of the fuel elements in the reactor core at the time of reactor shutdown to the reactor physics analysis software; wherein the burnup result request carries the input information required by the reactor physics analysis software; The receiving module 202 is used to receive the burnup results of the fuel elements in the reactor core returned by the reactor physics analysis software; wherein the burnup results include the activity values ​​of the characteristic nuclides of the fuel elements in the reactor core; The first determining module 203 is used to determine the decay variables of the characteristic nuclides of the fuel element in the unloading pipe based on the shutdown time; The second determining module 204 is used to determine the sorting limit of the characteristic nuclide based on the reactor state parameters before shutdown, the burnup results, and the decay variables. The third determining module 205 is used to determine the sorting result of the fuel element to be sorted based on the sorting limit, so as to distinguish the high and low enrichment of the fuel element to be sorted.

[0058] In one alternative implementation, the input information includes core power and the operating time of the high-temperature gas-cooled reactor.

[0059] In one optional implementation, the second determining module 204 includes: The first determining submodule is used to calculate the reactor state parameters before shutdown and the burnup results using VSOP to obtain the initial sorting limit of the characteristic nuclide; The second determining submodule is used to dynamically correct the initial sorting limit based on the decay variable to obtain the corrected sorting limit, and use the corrected sorting limit as the sorting limit of the feature nuclide.

[0060] In one optional implementation, the characteristic nuclides include multiple types, and the second determining module 204 is specifically used for: Based on the reactor state parameters before shutdown, the burnup results, and the decay variables, the sorting limits for each characteristic nuclide are determined. Accordingly, the third determining module 205 is specifically used for: Based on the sorting limits and confidence levels of each characteristic nuclide, the sorting results of the fuel elements to be sorted are determined.

[0061] In one optional implementation, the confidence level of each characteristic nuclide is determined based on the half-life of the corresponding characteristic nuclide, the activity value of the corresponding characteristic nuclide, and the shutdown time.

[0062] In one optional implementation, the third determining module 205 is specifically used for: Based on the sorting limit and the activity values ​​of the characteristic nuclides of the fuel element to be sorted sent by the spectrometer, the sorting result of the fuel element to be sorted is determined.

[0063] The high- and low-enrichment fuel element differentiation device for high-temperature gas-cooled reactors provided in this disclosure can execute the high- and low-enrichment fuel element differentiation method for high-temperature gas-cooled reactors provided in any embodiment of this disclosure, and has the corresponding functional modules and beneficial effects of executing the method.

[0064] This disclosure also provides a computer program product, including a computer program / instruction, which, when executed by a processor, implements the method for distinguishing high and low enrichment fuel elements in a high-temperature gas-cooled reactor as provided in this disclosure.

[0065] Figure 3 This is a schematic diagram of the structure of an electronic device provided in an embodiment of the present disclosure.

[0066] The following is a detailed reference. Figure 3The diagram illustrates a structural schematic suitable for implementing the electronic device 300 in the embodiments of this disclosure. The electronic device 300 in the embodiments of this disclosure may include, but is not limited to, mobile terminals such as mobile phones, laptops, digital broadcast receivers, personal digital assistants (PDAs), tablet computers (PADs), portable media players (PMPs), in-vehicle terminals (e.g., in-vehicle navigation terminals), and fixed terminals such as digital TVs and desktop computers. Figure 3 The electronic device shown is merely an example and should not be construed as limiting the functionality and scope of the embodiments disclosed herein.

[0067] like Figure 3 As shown, the electronic device 300 may include a processing unit 301 (e.g., a central processing unit, a graphics processing unit, etc.), which can perform various appropriate actions and processes according to a program stored in read-only memory (ROM) 302 or a program loaded from storage device 308 into random access memory (RAM) 303. The RAM 303 also stores various programs and data required for the operation of the electronic device 300. The processing unit 301, ROM 302, and RAM 303 are interconnected via a bus 304. An input / output (I / O) interface 305 is also connected to the bus 304.

[0068] Typically, the following devices can be connected to I / O interface 305: input devices 306 including, for example, touchscreens, touchpads, keyboards, mice, cameras, microphones, accelerometers, gyroscopes, etc.; output devices 307 including, for example, liquid crystal displays (LCDs), speakers, vibrators, etc.; storage devices 308 including, for example, magnetic tapes, hard disks, etc.; and communication devices 309. Communication device 309 allows electronic device 300 to communicate wirelessly or wiredly with other devices to exchange data. Although Figure 3 An electronic device 300 with various devices is shown; however, it should be understood that it is not required to implement or possess all of the devices shown. More or fewer devices may be implemented or possessed alternatively.

[0069] In particular, according to embodiments of this disclosure, the processes described above with reference to the flowcharts can be implemented as computer software programs. For example, embodiments of this disclosure include a computer program product comprising a computer program carried on a non-transitory computer-readable medium, the computer program containing program code for performing the methods shown in the flowcharts. In such embodiments, the computer program can be downloaded and installed from a network via communication device 309, or installed from storage device 308, or installed from ROM 302. When the computer program is executed by processing device 301, it performs the functions defined in the high-temperature gas-cooled reactor high- and low-enrichment fuel element differentiation method of embodiments of this disclosure.

[0070] It should be noted that the computer-readable medium described above in this disclosure can be a computer-readable signal medium or a computer-readable storage medium, or any combination thereof. A computer-readable storage medium can be, for example,—but not limited to—an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any combination thereof. More specific examples of a computer-readable storage medium may include, but are not limited to: an electrical connection having one or more wires, a portable computer disk, a hard disk, a random access memory, a read-only memory, an electrically erasable programmable read-only memory (EPROM), an optical fiber, a portable compact disc read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination thereof. In this disclosure, a computer-readable storage medium can be any tangible medium containing or storing a program that can be used by or in conjunction with an instruction execution system, apparatus, or device. In this disclosure, a computer-readable signal medium can include a data signal propagated in baseband or as part of a carrier wave, carrying computer-readable program code. The transmitted data signal can take various forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination thereof. The computer-readable signal medium can also be any computer-readable medium other than a computer-readable storage medium, which can send, propagate, or transmit a program for use by or in connection with an instruction execution system, apparatus, or device. The program code contained on the computer-readable medium can be transmitted using any suitable medium, including but not limited to: wires, optical fibers, radio frequency (RF), etc., or any suitable combination thereof.

[0071] In some implementations, clients and servers can communicate using any currently known or future-developed network protocol, such as Hypertext Transfer Protocol (HTTP), and can interconnect with digital data communication (e.g., communication networks) of any form or medium. Examples of communication networks include Local Area Networks (LANs), Wide Area Networks (WANs), the Internet (e.g., the Internet), and peer-to-peer networks (e.g., ad hoc peer-to-peer networks), as well as any currently known or future-developed networks.

[0072] The aforementioned computer-readable medium may be included in the aforementioned electronic device; or it may exist independently and not assembled into the electronic device.

[0073] The aforementioned computer-readable medium carries one or more programs that, when executed by the electronic device, cause the electronic device to: send a request to reactor physics analysis software for burnup results of fuel elements in the reactor core at the time of reactor shutdown; wherein the burnup result request carries input information required by the reactor physics analysis software; receive the burnup results of the fuel elements in the reactor core returned by the reactor physics analysis software; wherein the burnup results include the activity values ​​of characteristic nuclides of the fuel elements in the reactor core; determine the decay variables of the characteristic nuclides of the fuel elements in the discharge pipe based on the shutdown time; determine the sorting limits of the characteristic nuclides based on the reactor state parameters before shutdown, the burnup results, and the decay variables; and determine the sorting results of the fuel elements to be sorted based on the sorting limits, so as to distinguish between high and low enrichment of the fuel elements to be sorted.

[0074] Computer program code for performing the operations of this disclosure can be written in one or more programming languages ​​or a combination thereof, including but not limited to object-oriented programming languages ​​such as Java, Smalltalk, and C++, as well as conventional procedural programming languages ​​such as the "C" language or similar programming languages. The program code can be executed entirely on the user's computer, partially on the user's computer, as a standalone software package, partially on the user's computer and partially on a remote computer, or entirely on a remote computer or server. In cases involving remote computers, the remote computer can be connected to the user's computer via any type of network—including local area networks (LANs) or wide area networks (WANs), or it can be connected to an external computer (e.g., via the Internet using an Internet service provider).

[0075] The flowcharts and block diagrams in the accompanying drawings illustrate the architecture, functionality, and operation of possible implementations of systems, methods, and computer program products according to various embodiments of this disclosure. In this regard, each block in a flowchart or block diagram may represent a module, segment, or portion of code containing one or more executable instructions for implementing a specified logical function. It should also be noted that in some alternative implementations, the functions indicated in the blocks may occur in a different order than those indicated in the drawings. For example, two consecutively indicated blocks may actually be executed substantially in parallel, and they may sometimes be executed in reverse order, depending on the functions involved. It should also be noted that each block in the block diagrams and / or flowcharts, and combinations of blocks in the block diagrams and / or flowcharts, can be implemented using a dedicated hardware-based system that performs the specified function or operation, or using a combination of dedicated hardware and computer instructions.

[0076] The units described in the embodiments of this disclosure can be implemented in software or in hardware. The names of the units are not, in some cases, intended to limit the specific unit.

[0077] The functions described above in this document can be performed at least in part by one or more hardware logic components. For example, exemplary types of hardware logic components that can be used, without limitation, include: Field-Programmable Gate Array (FPGA), Application Specific Integrated Circuit (ASIC), Application Specific Standard Parts (ASSP), System on Chip (SOC), Complex Programmable Logic Device (CPLD), and so on.

[0078] In the context of this disclosure, a machine-readable medium can be a tangible medium that may contain or store a program for use by or in conjunction with an instruction execution system, apparatus, or device. A machine-readable medium can be a machine-readable signal medium or a machine-readable storage medium. Machine-readable media can be, but is not limited to, electronic, magnetic, optical, electromagnetic, infrared, or semiconductor systems, apparatus, or devices, or any suitable combination of the foregoing. More specific examples of machine-readable storage media include electrical connections based on one or more wires, portable computer disks, hard disks, random access memory, read-only memory, erasable programmable read-only memory, flash memory, optical fiber, portable compact disk read-only memory, optical storage devices, magnetic storage devices, or any suitable combination of the foregoing.

[0079] It is understood that before using the technical solutions disclosed in the various embodiments of this disclosure, users should be informed of the types, scope of use, and usage scenarios of the information involved in this disclosure in an appropriate manner in accordance with relevant laws and regulations, and user authorization should be obtained.

[0080] The above description is merely a preferred embodiment of this disclosure and an explanation of the technical principles employed. Those skilled in the art should understand that the scope of this disclosure is not limited to technical solutions formed by specific combinations of the above-described technical features, but should also cover other technical solutions formed by arbitrary combinations of the above-described technical features or their equivalents without departing from the above-described concept. For example, technical solutions formed by substituting the above features with (but not limited to) technical features disclosed in this disclosure that have similar functions.

[0081] Furthermore, while the operations are described in a specific order, this should not be construed as requiring these operations to be performed in the specific order shown or in a sequential order. In certain environments, multitasking and parallel processing may be advantageous. Similarly, while several specific implementation details are included in the above discussion, these should not be construed as limiting the scope of this disclosure. Certain features described in the context of individual embodiments may also be implemented in combination in a single embodiment. Conversely, various features described in the context of a single embodiment may also be implemented individually or in any suitable sub-combination in multiple embodiments.

[0082] Although the subject matter has been described using language specific to structural features and / or methodological logic, it should be understood that the subject matter defined in the appended claims is not necessarily limited to the specific features or actions described above. Rather, the specific features and actions described above are merely illustrative examples of implementing the claims.

Claims

1. A method for distinguishing high and low enrichment fuel elements in a high-temperature gas-cooled reactor, characterized in that, The method includes: Send a request to the reactor physics analysis software for the burnup results of the fuel elements in the reactor core at the time of reactor shutdown; wherein the burnup result request carries the input information required by the reactor physics analysis software; The reactor receives the burnup results of the fuel elements within the reactor core returned by the reactor physics analysis software; wherein the burnup results include the activity values ​​of the characteristic nuclides of the fuel elements within the reactor core. The decay variables of the characteristic nuclides of the fuel elements within the unloading pipe are determined based on the reactor shutdown time; Based on the reactor state parameters before shutdown, the burnup results, and the decay variables, the sorting limits for characteristic nuclides are determined. Based on the sorting limit, the sorting result of the fuel element to be sorted is determined in order to distinguish between high and low enrichment of the fuel element to be sorted.

2. The method according to claim 1, characterized in that, The input information includes core power and the operating time of the high-temperature gas-cooled reactor.

3. The method according to claim 1, characterized in that, The step of determining the sorting limit for characteristic nuclides based on the reactor state parameters before shutdown, the burnup results, and the decay variables includes: The initial sorting limits for characteristic nuclides are obtained by using VSOP to calculate the reactor state parameters before shutdown and the burnup results. The initial sorting limit is dynamically corrected based on the decay variable to obtain the corrected sorting limit, and the corrected sorting limit is used as the sorting limit for the characteristic nuclide.

4. The method according to claim 1, characterized in that, The characteristic nuclides include multiple types. Determining the sorting limits for the characteristic nuclides based on the reactor state parameters before shutdown, the burnup results, and the decay variables includes: Based on the reactor state parameters before shutdown, the burnup results, and the decay variables, the sorting limits for each characteristic nuclide are determined. Accordingly, determining the sorting result of the fuel element to be sorted based on the sorting limit includes: Based on the sorting limits and confidence levels of each characteristic nuclide, the sorting results of the fuel elements to be sorted are determined.

5. The method according to claim 4, characterized in that, The confidence level of each characteristic nuclide is determined based on the half-life of the corresponding characteristic nuclide, the activity value of the corresponding characteristic nuclide, and the shutdown time.

6. The method according to claim 1, characterized in that, The process of determining the sorting result of the fuel element to be sorted based on the sorting limit includes: Based on the sorting limit and the activity values ​​of the characteristic nuclides of the fuel element to be sorted sent by the spectrometer, the sorting result of the fuel element to be sorted is determined.

7. A device for differentiating high and low enrichment fuel elements in a high-temperature gas-cooled reactor, characterized in that, The device includes: The sending module is used to send a request for the burnup results of the fuel elements in the reactor core at the time of reactor shutdown to the reactor physics analysis software; wherein the burnup result request carries the input information required by the reactor physics analysis software; A receiving module is used to receive the burnup results of the fuel elements in the reactor core returned by the reactor physics analysis software; wherein the burnup results include the activity values ​​of the characteristic nuclides of the fuel elements in the reactor core; The first determining module is used to determine the decay variables of the characteristic nuclides of the fuel element in the unloading pipe based on the shutdown time; The second determining module is used to determine the sorting limit of the characteristic nuclide based on the reactor state parameters before shutdown, the burnup results, and the decay variables. The third determining module is used to determine the sorting result of the fuel element to be sorted based on the sorting limit, so as to distinguish the high and low enrichment of the fuel element to be sorted.

8. An electronic device, characterized in that, The electronic device includes: processor; Memory used to store the processor's executable instructions; The processor is configured to read the executable instructions from the memory and execute the executable instructions to implement the method for distinguishing high and low enrichment fuel elements in a high-temperature gas-cooled reactor as described in any one of claims 1-6.

9. A computer-readable storage medium, characterized in that, The storage medium stores a computer program for executing the high- and low-enrichment fuel element differentiation method for high-temperature gas-cooled reactors as described in any one of claims 1-6.

10. A computer program product comprising a computer program / instructions, characterized in that, When the computer program / instruction is executed by the processor, it implements the method for distinguishing high and low enrichment fuel elements in a high-temperature gas-cooled reactor as described in any of claims 1-6.

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