Nuclear fuel management method and device for multi-module pebble-bed high-temperature gas cooled reactor

Abstract

The invention relates to the technical field of reactor fuel management, in particular to a nuclear fuel management method of a multi-module pebble-bed high-temperature gas cooled reactor. The method comprises the following steps: according to first input information corresponding to a multi-module pebble-bed high-temperature gas cooled reactor, obtaining first fuel management information in a first module initial loading reactor and a transition process; according to the low-enrichment-degree light-burn-up spent fuel element information corresponding to the first module and second input information corresponding to the second module, second fuel management information in the initial loading and transition process of the second module is obtained; according to the low-enrichment-degree light-burn-up spent fuel element information corresponding to at least one third module and the second input information corresponding to the fourth module, third fuel management information in the initial loading and transition process of the fourth module is obtained; and in the process of executing the fuel management information set, executing the fuel management information set according to the evaluation result of the fuel management information set. The accuracy of nuclear fuel management can be improved, and the utilization rate of fuel elements is increased.

Description

Technical Field

[0001] The present disclosure relates to the technical field of reactor fuel management, and in particular to a nuclear fuel management method for a multi-module pebble bed high-temperature gas-cooled reactor. Background Art

[0002] The pebble-bed high-temperature gas-cooled reactor (HTGR) utilizes spherical fuel elements, graphite as a moderator, and helium as a coolant. Hundreds of thousands of these spherical fuel elements are loaded into the reactor to achieve criticality, enabling continuous and stable operation. During operation, spherical fuel elements are continuously loaded into the core from the top and simultaneously unloaded from the bottom, maintaining a constant core load. Therefore, fuel element management during initial loading and transition phases is a key concern for HTGRs. Summary of the Invention

[0003] The present disclosure provides a nuclear fuel management method for a multi-module pebble bed high-temperature gas-cooled reactor, which can improve the accuracy of nuclear fuel management and increase the utilization rate of fuel elements. The technical solution of the present disclosure is as follows: According to a first aspect of an embodiment of the present disclosure, a nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor is provided, comprising: obtaining, according to first input information corresponding to a multi-module pebble bed high temperature gas-cooled reactor, first fuel management information during initial stacking and transition of a first module, wherein the first module is the first module of the multiple modules; acquiring, based on the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module, second fuel management information during the initial stacking and transition process of the second module, wherein the second module is the next module adjacent to the first module in the multiple modules; obtaining, based on low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to a fourth module, third fuel management information during initial stacking and transition of the fourth module, wherein the third module is a module preceding the fourth module in the multiple modules, and the fourth module is any module in the multiple modules other than the first module and the second module; During the execution of the fuel management information set, the fuel management information set is evaluated using a security evaluation method, and the fuel management information set is executed based on the evaluation result, wherein the fuel management information set includes the first fuel management information, the second fuel management information and the third fuel management information.

[0004] According to some embodiments, the method further comprises: When a plurality of fuel management information sets corresponding to the plurality of modules are determined, obtaining evaluation information corresponding to each fuel management information set in the plurality of fuel management information sets; A target fuel management information set is obtained according to the evaluation information corresponding to each fuel management information set.

[0005] According to some embodiments, obtaining first fuel management information during initial installation and transition of the first module based on first input information corresponding to the multi-module pebble bed high temperature gas-cooled reactor includes: Obtain structural design information of the multi-module pebble bed type high temperature gas-cooled reactor, power information of the multi-module pebble bed type high temperature gas-cooled reactor, and design information of the multi-module pebble bed type high temperature gas-cooled reactor; obtain first fuel management information during the initial installation and transition process of the first module, wherein the first fuel management information includes at least one of core loading information, fuel element enrichment information, fuel element and graphite ball ratio information, initial core establishment process information, transition process information, spent fuel sorting limit information, loading and replacement method information, and reactivity control information.

[0006] According to some embodiments, obtaining the second fuel management information of the second module during initial stacking and transition based on the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module includes: Acquiring low-enrichment shallow burnup spent fuel element information corresponding to the first module, wherein the low-enrichment shallow burnup spent fuel element information corresponding to the first module includes quantity information and unloading burnup information of the low-enrichment shallow burnup spent fuel elements corresponding to the first module; Based on the quantity information of the low-enrichment and shallow-burnup spent fuel elements corresponding to the first module, the unloading burnup information, the fuel element information corresponding to the second module, and the graphite ball information corresponding to the second module, second fuel management information of the second module during the initial loading and transition process is obtained, wherein the second fuel management information includes at least one of core loading capacity information, fuel element enrichment information, mixed fuel element and graphite ball ratio information, initial core establishment process information, transition process information, spent fuel sorting limit information, loading and replacement method information, and reactivity control information, and the mixed fuel elements include the low-enrichment and shallow-burnup spent fuel elements corresponding to the first module and the fuel elements corresponding to the second module.

[0007] According to some embodiments, the method further comprises: When there are multiple units corresponding to the multi-module pebble bed high temperature gas-cooled reactor, the fuel management information set is adjusted according to the demand information of the multi-module pebble bed high temperature gas-cooled reactor of each unit in the multiple units to obtain a first adjusted fuel management information set.

[0008] According to some embodiments, executing the fuel management information collection according to the evaluation result includes: If the evaluation result indicates that the operating parameters of the multi-module pebble bed high temperature gas-cooled reactor during initial installation and transition meet parameter requirements, continuing to execute the fuel management information set; or, When the evaluation result indicates that the operating parameters during the initial installation and transition of the multi-module pebble bed high temperature gas-cooled reactor do not meet the parameter requirements, the fuel management information set is adjusted, and a second adjusted fuel management information set is obtained and executed.

[0009] According to some embodiments, the operating parameter includes at least one of a maximum operating temperature, a maximum accident temperature, and a single-ball power.

[0010] According to a second aspect of an embodiment of the present disclosure, a nuclear fuel management device for a multi-module pebble bed high temperature gas-cooled reactor is provided, comprising: an information acquisition unit, configured to acquire first fuel management information of a first module during initial installation and transition based on first input information corresponding to a multi-module pebble bed high temperature gas-cooled reactor, wherein the first module is the first module among the multiple modules; The information acquisition unit is further configured to acquire second fuel management information of the second module during initial stacking and transition based on the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module, wherein the second module is the next module adjacent to the first module in the multiple modules; The information acquisition unit is further configured to acquire third fuel management information of the fourth module during initial stacking and transition based on low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to a fourth module, wherein the third module is a module preceding the fourth module in the multiple modules, and the fourth module is any module in the multiple modules other than the first module and the second module; An information execution unit is configured to evaluate the fuel management information set using a security evaluation method during execution of the fuel management information set, and execute the fuel management information set according to the evaluation result, wherein the fuel management information set includes the first fuel management information, the second fuel management information, and the third fuel management information. According to a third aspect of an embodiment of the present disclosure, there is provided an electronic device comprising: processor; a memory for storing instructions executable by the processor; The processor is configured to execute the instructions to implement the nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor as described in any one of the aforementioned aspects.

[0011] According to a fourth aspect of an embodiment of the present disclosure, a storage medium is provided. When the instructions in the storage medium are executed by a processor of an electronic device, the electronic device is enabled to execute the nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor described in any one of the aforementioned aspects.

[0012] According to a fifth aspect of an embodiment of the present disclosure, a computer program product is provided, comprising a computer program, wherein the computer program implements any one of the methods described in the preceding aspects when executed by a processor.

[0013] The technical solutions provided by the embodiments of the present disclosure bring at least the following beneficial effects: In some or related embodiments, first fuel management information of the first module during initial installation and transition is obtained according to first input information corresponding to a multi-module pebble bed high temperature gas-cooled reactor, wherein the first module is the first module among the multiple modules; second fuel management information of the second module during initial installation and transition is obtained according to low-enrichment shallow burnup spent fuel element information corresponding to the first module and second input information corresponding to the second module, wherein the second module is the next module adjacent to the first module among the multiple modules; third fuel management information of the fourth module during initial installation and transition is obtained according to low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to a fourth module, wherein the third module is the module before the fourth module among the multiple modules, and the fourth module is any module among the multiple modules except the first module and the second module; in the process of executing the fuel management information set, the fuel management information set is evaluated using a safety evaluation method, and the fuel management information set is executed according to the evaluation result, wherein the fuel management information set includes the first fuel management information, the second fuel management information and the third fuel management information. Therefore, the first module can be determined based on the input information, and the modules after the first module can use the low-enrichment and shallow burnup fuel elements of the previous module in the transition process of the subsequent module stack, which can improve the accuracy of the fuel management information determination, shorten the transition process time, reduce the time to reach a balanced core, and reduce the cost of the power plant. The low-enrichment and shallow burnup fuel elements can be returned to the stack for utilization, which can improve the utilization efficiency of the low-enrichment and shallow burnup fuel elements, reduce the demand for new low-enrichment fuel elements, and reduce the nuclear fuel operating cost of the unit. It also reduces the number of low-enrichment spent fuel elements accordingly, reduces the storage and post-processing costs of the spent fuel elements, and thus improves the utilization rate of the low-enrichment fuel elements and reduces the cost of nuclear fuel.

[0014] 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 disclosure. BRIEF DESCRIPTION OF THE DRAWINGS

[0015] The accompanying drawings herein are incorporated into and constitute a part of the specification, illustrate embodiments consistent with the present disclosure, and together with the description are used to explain the principles of the present disclosure, and do not constitute an improper limitation of the present disclosure.

[0016] Figure 1 This is a flow chart of a first nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor provided by an embodiment of the present disclosure; Figure 2 This is a flow chart of a second nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor provided by an embodiment of the present disclosure; Figure 3 This is a schematic diagram illustrating an example structure of a spherical fuel element provided by an embodiment of the present disclosure; Figure 4 This is a schematic diagram illustrating an example of burnup changes during unloading of low-enrichment fuel elements in a pebble-bed high-temperature gas-cooled reactor according to an embodiment of the present disclosure; Figure 5 This is a block diagram of a nuclear fuel management device for a multi-module pebble bed high temperature gas-cooled reactor according to an exemplary embodiment; Figure 6 The figure is a schematic diagram showing an example of an electronic device according to an exemplary embodiment. DETAILED DESCRIPTION

[0017] In order to enable ordinary persons in the art to better understand the technical solutions of the present disclosure, the technical solutions in the embodiments of the present disclosure will be clearly and completely described below with reference to the accompanying drawings.

[0018] The present disclosure provides a nuclear fuel management method, device, electronic device, and storage medium for a multi-module pebble-bed high-temperature gas-cooled reactor. In some embodiments, the terms "nuclear fuel management method for a multi-module pebble-bed high-temperature gas-cooled reactor" and "information processing method" and "communication method" are interchangeable; the terms "nuclear fuel management device for a multi-module pebble-bed high-temperature gas-cooled reactor" and "information processing device" and "communication device" are interchangeable; and the terms "information processing system" and "communication system" are interchangeable.

[0019] The embodiments of the present disclosure are not exhaustive and are merely illustrative of some embodiments, and are not intended to be a specific limitation on the scope of protection of the present disclosure. In the absence of contradiction, each step in a certain embodiment can be implemented as an independent embodiment, and the steps can be arbitrarily combined. For example, a solution after removing some steps in a certain embodiment can also be implemented as an independent embodiment, and the order of the steps in a certain embodiment can be arbitrarily exchanged. In addition, the optional implementation methods in a certain embodiment can be arbitrarily combined; in addition, the embodiments can be arbitrarily combined. For example, some or all steps of different embodiments can be arbitrarily combined, and a certain embodiment can be arbitrarily combined with the optional implementation methods of other embodiments.

[0020] In each embodiment of the present disclosure, unless otherwise specified or provided for by logic, the terms and / or descriptions between the embodiments are consistent and can be referenced by each other. The technical features in different embodiments can be combined to form a new embodiment based on their inherent logical relationships.

[0021] The terms used in the embodiments of the present disclosure are only for the purpose of describing specific embodiments and are not intended to limit the present disclosure.

[0022] In the embodiments of the present disclosure, unless otherwise specified, elements expressed in the singular, such as "a", "an", "the", "above", "said", "the", "the", etc., may mean "one and only one", or "one or more", "at least one", etc. For example, when using articles such as "a", "an", "the" in English in translation, the noun following the article may be understood as a singular expression or a plural expression.

[0023] In the embodiments of the present disclosure, “plurality” refers to two or more.

[0024] In some embodiments, the terms “at least one,” “one or more,” “a plurality of,” “multiple,” etc. may be used interchangeably.

[0025] The prefixes such as "first" and "second" in the embodiments of the present disclosure are only used to distinguish different description objects and do not constitute any restriction on the position, order, priority, quantity or content of the description objects. For the statement of the description object, please refer to the description in the context of the claims or embodiments, and no unnecessary restriction should be constituted due to the use of prefixes. For example, if the description object is a "field", the ordinal number before the "field" in the "first field" and the "second field" does not limit the position or order between the "fields". "First" and "second" do not limit whether the "fields" they modify are in the same message, nor do they limit the order of the "first field" and the "second field". For another example, if the description object is a "level", the ordinal number before the "level" in the "first level" and the "second level" does not limit the priority between the "levels". For another example, the number of description objects is not limited by the ordinal number and can be one or more. Taking "first device" as an example, the number of "devices" can be one or more. In addition, the objects modified by different prefixes can be the same or different. For example, if the description object is "device", then the "first device" and the "second device" can be the same device or different devices, and their types can be the same or different; for another example, if the description object is "information", then the "first information" and the "second information" can be the same information or different information, and their contents can be the same or different.

[0026] In some embodiments, "terminal" or "terminal device" may be referred to as "user equipment (UE)", "user terminal", "mobile station (MS)", "mobile terminal (MT)", subscriber station, mobile unit, subscriber unit, wireless unit, remote unit, mobile device, wireless device, wireless electronic device (wireless communication device), remote device, mobile subscriber station, access terminal, mobile terminal, wireless terminal, remote terminal, handset, user agent, mobile client, client, etc.

[0027] In some embodiments, data, information, etc. may be obtained with the user's consent.

[0028] It should be noted that the terms "first," "second," and the like in the specification and claims of the present disclosure and the above-mentioned drawings are used to distinguish similar objects and are not necessarily used to describe a specific order or precedence. It should be understood that the numbers used in this manner are interchangeable where appropriate so that the embodiments of the present disclosure described herein can be implemented in an order other than those illustrated or described herein. The embodiments described in the following exemplary embodiments do not represent all embodiments consistent with the present disclosure. Instead, they are merely examples of apparatus and methods consistent with certain aspects of the present disclosure as detailed in the appended claims.

[0029] Figure 1 This is a flow chart of a first method for managing nuclear fuel for a multi-module pebble bed high temperature gas-cooled reactor provided by an embodiment of the present disclosure. Figure 1 As shown, the nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor can be used in the nuclear fuel management scenarios of the initial installation and transition process of the multi-module pebble bed high temperature gas-cooled reactor, and includes the following steps: In step S11, first fuel management information of the first module during initial installation and transition is obtained according to first input information corresponding to the multi-module pebble bed high temperature gas-cooled reactor, wherein the first module is the first module in the multi-module; In some embodiments, the execution subject of the embodiments of the present disclosure may be, for example, an electronic device. The electronic device does not specifically refer to a fixed electronic device. For example, when the device identification changes, the electronic device may also change accordingly. For example, when the structure of the electronic device changes, the electronic device may also change accordingly. Among them, the execution subject of the embodiments of the present disclosure may also be, for example, a server. The server may be, for example, a single server or a server cluster, and the embodiments of the present disclosure are not limited to this.

[0030] According to some embodiments, a multi-module pebble bed high temperature gas-cooled reactor can be, for example, a reactor that uses spherical fuel elements, graphite as a moderator, and helium as a coolant. The most notable fuel management feature of this type of reactor is that it can be refueled without stopping the reactor, that is, it can be loaded and refueled during operation. The multi-module pebble bed high temperature gas-cooled reactor does not specifically refer to a fixed reactor. For example, when the number of modules corresponding to the multi-module pebble bed high temperature gas-cooled reactor changes, the multi-module pebble bed high temperature gas-cooled reactor can also change accordingly. For example, when the spherical fuel elements change, the multi-module pebble bed high temperature gas-cooled reactor can also change accordingly.

[0031] The "high temperature" in a high-temperature gas-cooled reactor (HTGR) may, for example, refer to the outlet temperature of the reactor coolant (usually helium) being greater than a preset temperature, for example, higher than that of a water-cooled reactor. The temperature of a high-temperature gas-cooled reactor can reach 700°C to 950°C, or even greater than 950°C.

[0032] In some embodiments, the first input information may be, for example, input information corresponding to the first module. Different modules may correspond to different input information. The first input information may be, for example, input information corresponding to the first module, specifically information input to the first module. The first in the first input information is used to distinguish it from the remaining input information and does not specifically refer to a fixed information. For example, when the amount of information in the first input information changes, the first input information may also change accordingly. For example, when the specific information in the first input information changes, the first input information may also change accordingly.

[0033] According to some embodiments, the first module type may be the first module in a multi-module pebble bed high-temperature gas-cooled reactor, i.e., the first module among multiple modules. The first module does not specifically refer to a fixed module. For example, if the module identifier of the first module changes, the first module may also change accordingly.

[0034] According to some embodiments, a "pre-loaded" reactor refers to a state in which the core active area is completely filled with a uniform mixture of fuel elements and graphite spheres, and the reactivity is sufficient for full power operation. A "transition process" may, for example, refer to the transition from a "pre-loaded" state to an equilibrium state, and may involve analysis of criticality, power variation, burnup variation, and other conditions.

[0035] According to some embodiments, the first fuel management information may, for example, refer to combustion management information for the first module during initial stack installation and transition. This combustion management information does not specifically refer to fixed information. For example, if the first input information changes, the first combustion management information may also change accordingly. The first in the first combustion management information is used to distinguish it from the remaining combustion management information. For example, if the number of information corresponding to the first combustion management information changes, the first combustion management information may also change accordingly.

[0036] In some embodiments, first fuel management information during initial installation and transition of a first module is obtained based on first input information corresponding to a multi-module pebble bed high temperature gas-cooled reactor, wherein the first module is the first module among the multiple modules.

[0037] In step S12, second fuel management information of the second module during initial stacking and transition is obtained based on the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module, wherein the second module is the next module adjacent to the first module in the multiple modules; According to some embodiments, the low-enrichment, shallow burnup spent fuel element information corresponding to the first module may, for example, be information related to low-enrichment, shallow burnup spent fuel elements discharged by the first module. The low-enrichment, shallow burnup spent fuel element information corresponding to the first module may, for example, include quantity and discharge burnup. The low-enrichment, shallow burnup spent fuel element information corresponding to the first module does not specifically refer to fixed information. For example, if the number of low-enrichment, shallow burnup spent fuel elements corresponding to the first module changes, the low-enrichment, shallow burnup spent fuel element information corresponding to the first module may also change accordingly.

[0038] In some embodiments, the second module may be, for example, the next module adjacent to the first module in the plurality of modules, i.e., the second module in the plurality of modules. The "second" in the second module is used to distinguish it from the remaining modules and does not specifically refer to a fixed module.

[0039] According to some embodiments, the second input information may be, for example, input information corresponding to the second module, wherein different modules may correspond to different input information. The second fuel management information may be, for example, fuel management information corresponding to the second module.

[0040] In some embodiments, second fuel management information of the second module during initial stacking and transition is obtained based on low-enrichment shallow burnup spent fuel element information corresponding to the first module and second input information corresponding to the second module, wherein the second module is the next module adjacent to the first module among multiple modules.

[0041] In step S13, third fuel management information of the fourth module during initial stacking and transition is obtained based on low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to the fourth module, wherein the third module is a module before the fourth module in the multiple modules, and the fourth module is any module in the multiple modules except the first module and the second module; According to some embodiments, the third module is multiple modules or all modules preceding the fourth module in the multi-module system. The fourth module is any module in the multi-module system except the first and second modules. Specifically, the fuel management information for the third module and subsequent modules in the multi-module system can be determined based on the input information of the module and the low-enrichment, shallow-burnup spent fuel element information of all previous modules.

[0042] In some embodiments, the fuel management information of the third module and each module after the third module of the multi-module can be jointly determined based on the input information of the module and the low-enrichment shallow burnup spent fuel element information of at least one previous module.

[0043] In some embodiments, third fuel management information of the fourth module during the initial stacking and transition process is obtained based on low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to the fourth module, wherein the third module is the module before the fourth module in the multiple modules, and the fourth module is any module in the multiple modules except the first module and the second module.

[0044] In step S14, during the execution of the fuel management information set, the fuel management information set is evaluated using a safety evaluation method, and the fuel management information set is executed according to the evaluation result, wherein the fuel management information set includes the first fuel management information, the second fuel management information and the third fuel management information.

[0045] According to some embodiments, a safety assessment method may be, for example, a method for determining whether each fuel management information in a fuel management information set is safely executed. The safety assessment method may be, for example, applicable to multiple modules or specific to each module. The safety assessment method may include, for example, one or more of the following: maximum operating temperature, maximum accident temperature, and single-bulb power.

[0046] In some embodiments, the fuel management information set may include, for example, first fuel management information, second fuel management information, and third fuel management information. That is, each piece of fuel management information needs to be evaluated.

[0047] According to some embodiments, during the execution of a fuel management information set, the fuel management information set is evaluated using a security evaluation method, and the fuel management information set is executed based on the evaluation result, wherein the fuel management information set includes first fuel management information, second fuel management information, and third fuel management information.

[0048] In some or related embodiments, first fuel management information of the first module during initial installation and transition is obtained according to first input information corresponding to a multi-module pebble bed high temperature gas-cooled reactor, wherein the first module is the first module among the multiple modules; second fuel management information of the second module during initial installation and transition is obtained according to low-enrichment shallow burnup spent fuel element information corresponding to the first module and second input information corresponding to the second module, wherein the second module is the next module adjacent to the first module among the multiple modules; third fuel management information of the fourth module during initial installation and transition is obtained according to low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to the fourth module, wherein the third module is the module before the fourth module among the multiple modules, and the fourth module is any module among the multiple modules except the first module and the second module; in the process of executing the fuel management information set, the fuel management information set is evaluated using a safety evaluation method, and the fuel management information set is executed according to the evaluation result, wherein the fuel management information set includes the first fuel management information, the second fuel management information and the third fuel management information. Therefore, the first module can determine, based on the input information, that the modules subsequent to the first module can use the low-enrichment, shallow burnup fuel elements of the previous module in the transition process of the subsequent module reactor. That is, the loading time difference between the modules can be utilized to use the low-enrichment, shallow burnup spent fuel elements unloaded from the module reactor that was put into operation earlier in the transition process of the subsequent module reactor. This can improve the accuracy of the determination of the fuel management information, shorten the duration of the transition process, reduce the time to reach a balanced core, and reduce the cost of the power plant. The low-enrichment, shallow burnup fuel elements can be returned to the reactor for reuse, which can improve the utilization efficiency of the low-enrichment, shallow burnup fuel elements, reduce the demand for new low-enrichment fuel elements, and reduce the nuclear fuel operating cost of the unit. In addition, the number of low-enrichment spent fuel elements is correspondingly reduced, and the storage and post-processing costs of the spent fuel elements are reduced, thereby improving the utilization rate of the low-enrichment fuel elements and reducing the cost of nuclear fuel.

[0049] Figure 2 This is a flow chart of a second method for managing nuclear fuel for a multi-module pebble bed high temperature gas-cooled reactor provided by an embodiment of the present disclosure. Figure 2 As shown, the nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor can be used in the nuclear fuel management scenarios of the initial installation and transition process of the multi-module pebble bed high temperature gas-cooled reactor, and includes the following steps: In step S21, first fuel management information of the first module during initial installation and transition is obtained based on first input information corresponding to the multi-module pebble bed high temperature gas-cooled reactor, wherein the first module is the first module in the multi-module; The relevant description may be as described above, and will not be repeated here.

[0050] In some embodiments, a pebble bed high temperature gas-cooled reactor can, for example, load hundreds of thousands of spherical fuel elements into the reactor to reach a critical state where it can operate continuously and stably. During operation, spherical fuel elements can, for example, be continuously loaded into the core from the top of the reactor, while a corresponding number of fuel elements can be continuously unloaded from the bottom of the core to keep the core loading capacity unchanged. The unloaded fuel elements are measured for burnup by a burnup measurement system. If the predetermined burnup depth is not reached, they are returned to the reactor for use; fuel elements that have reached the predetermined burnup will be unloaded from the core as spent fuel and stored in the spent fuel tank. The structure of the spherical fuel elements can, for example, be as follows: Figure 3 As shown, where P y The C layer is the pyrolytic carbon layer. Figure 4 As shown. Figure 4 As shown in Figure 1, most low-enrichment fuel elements are not completely used up before being discharged from the core as spent fuel elements, which causes great economic waste. Therefore, reusing low-enrichment fuel elements can reduce costs.

[0051] According to some embodiments, during the initial installation and early stages of the transition process of a pebble-bed high-temperature gas-cooled reactor, the core produces limited fission products and is essentially free of neutron poisons. Therefore, compared to a balance core, less fissile material is required to achieve criticality. Therefore, the initial installation core of a pebble-bed high-temperature gas-cooled reactor can, for example, be composed of low-enrichment fuel elements (compared to the high-enrichment fuel elements of a balance core. For example, the core of a high-temperature gas-cooled reactor can be composed of a mixture of high- and low-enrichment fuel elements and graphite spheres, where the enrichment of the high- and low-enrichment fuel elements can be, for example, 8.5% and 4.2%, respectively). The graphite spheres can, for example, be pure graphite elements, of the same size as the fuel elements, and contain no uranium.

[0052] According to some embodiments, a pebble bed high temperature gas-cooled reactor uses a fuel mixture of unused low-enrichment fuel elements and graphite balls in a certain ratio to establish the initial core. After the initial core is established, a transition process is required to reach the equilibrium core. The ratio of unused low-enrichment fuel elements to graphite balls can be, for example, 7:8, which is not limited in the present embodiment. The above process may include: (1) The reactor is operated at a constant power level, with graphite spheres removed in batches and the same number of low-enrichment fuel elements simultaneously loaded. This results in the core's total mixed fuel load remaining constant, the number of graphite spheres gradually decreasing, and the number of low-enrichment fuel elements gradually increasing, until the core is entirely composed of low-enrichment fuel elements. Subsequently, the core will begin to discharge low-enrichment spent fuel elements (lower burnup levels).

[0053] (2) The reactor continues to operate at a certain power level, continuously discharging low-enrichment spent fuel elements (the discharge burnup gradually increases). As the low-enrichment spent fuel elements are discharged, an equal amount of high-enrichment fuel elements are loaded. This manifests as the total amount of core fuel elements remaining unchanged, the number of low-enrichment fuel elements gradually decreasing, and the number of high-enrichment fuel elements gradually increasing, until the core is entirely composed of high-enrichment fuel elements, reaching a balanced core state.

[0054] In some embodiments, for a multi-module pebble-bed high-temperature gas-cooled reactor, since each module is loaded and commissioned sequentially, there may be a time difference between the loading of the first and last modules, such as six months. If the same initial load and transition plan is used, the time required for each module is the same, for example, approximately three years of cumulative full-power operation, or approximately 1,100 effective full-power days (EFPD). Therefore, a nuclear fuel management plan for the unit's initial load and transition can be developed, and initial load and transition plans for each module can be prepared as input to the development of the nuclear fuel management plan.

[0055] According to some embodiments, obtaining first fuel management information during initial installation and transition of a first module based on first input information corresponding to a multi-module pebble bed high temperature gas-cooled reactor includes: Structural design information, power information, and design information of the multi-module pebble-bed high-temperature gas-cooled reactor are obtained, and first fuel management information for the first module during initial installation and transition is obtained. The first fuel management information includes at least one of core loading information, fuel element enrichment information, fuel element and graphite ball ratio information, initial core installation process information, transition process information, spent fuel sorting limit information, loading and replacement method information, and reactivity control information. Therefore, the fuel management information can be determined based on the corresponding input information, thereby improving the accuracy of the fuel management information determination and the accuracy of fuel management in the first module.

[0056] In some embodiments, the first module cannot utilize low-enrichment, shallow-burnup spent fuel elements from other modules for transition. Therefore, fuel management information for the first module needs to be determined. The quantity and burnup of low-enrichment, shallow-burnup spent fuel elements discharged from the first module during transition will be used to select fuel management plans for subsequent module initial loading and transition processes.

[0057] In step S22, second fuel management information of the second module during initial stacking and transition is obtained based on the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module, wherein the second module is the next module adjacent to the first module in the multiple modules; The relevant description may be as described above, and will not be repeated here.

[0058] According to some embodiments, obtaining second fuel management information of the second module during initial stacking and transition based on low-enrichment shallow burnup spent fuel element information corresponding to the first module and second input information corresponding to the second module includes: Obtaining low-enrichment shallow burnup spent fuel element information corresponding to the first module, wherein the low-enrichment shallow burnup spent fuel element information corresponding to the first module includes quantity information and unloading burnup information of the low-enrichment shallow burnup spent fuel elements corresponding to the first module; Based on the quantity information of low-enrichment, shallow burnup spent fuel elements corresponding to the first module, unloading burnup information, fuel element information corresponding to the second module, and graphite sphere information corresponding to the second module, second fuel management information for the initial stacking and transition processes of the second module is obtained. The second fuel management information includes at least one of core loading information, fuel element enrichment information, mixed fuel element and graphite sphere ratio information, initial core setup process information, transition process information, spent fuel sorting limit information, loading and refueling method information, and reactivity control information. The mixed fuel elements include low-enrichment, shallow burnup spent fuel elements corresponding to the first module and fuel elements corresponding to the second module. Therefore, the second fuel management information can be determined using the low-enrichment, shallow burnup spent fuel element information corresponding to the first module, allowing the low-enrichment, shallow burnup fuel elements to be used in the transition process of subsequent modules, shortening the transition process, reducing the time to reach a balanced core, and reducing power plant costs.

[0059] In some embodiments, the second module, such as Module 2, can be transitioned based on the unused fuel and spent fuel elements from Module 1. The quantity and unloading burnup of the spent fuel elements from Module 1 will inform the selection of nuclear fuel management plans for the initial load and transition process for modules 3 and beyond.

[0060] In step S23, third fuel management information of the fourth module during initial stacking and transition is obtained based on low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to the fourth module, wherein the third module is a module before the fourth module in the multiple modules, and the fourth module is any module in the multiple modules except the first module and the second module; The relevant description may be as described above, and will not be repeated here.

[0061] For example, the third module can transition using new fuel elements and spent fuel elements from the first and second modules, expanding fuel loading options. The quantity and burnup of spent fuel elements removed from the third module during transition will inform the initial and transition fuel management plans for modules 4 and beyond. Similarly, initial and transition fuel management plans can be developed for modules up to the nth module.

[0062] In some embodiments, there are theoretically many nuclear fuel management schemes for the initial installation and transition process of a multi-module pebble bed high temperature gas-cooled reactor, depending on different operating requirements, application scenarios, initial installation and transition process plans, etc., which can correspond to multiple fuel management information sets.

[0063] According to some embodiments, the method further comprises: In a case where a plurality of fuel management information sets corresponding to the plurality of modules are determined, obtaining evaluation information corresponding to each fuel management information set in the plurality of fuel management information sets; The target fuel management information set is obtained based on the evaluation information corresponding to each fuel management information set. In the case of multiple fuel management information sets, the target fuel management information set can be determined based on the evaluation information, which can improve the compatibility of the fuel management information set with multiple modules.

[0064] According to some embodiments, for example, multiple iterations, comparisons, and comprehensive analyses may be performed on multiple fuel management information sets to select a target fuel management information set.

[0065] According to some embodiments, when there are multiple units corresponding to a multi-module pebble-bed high-temperature gas-cooled reactor, the fuel management information set is adjusted based on the demand information of each of the multiple units to obtain a first adjusted fuel management information set. Thus, spent fuel elements discharged from the first-loaded module reactor can be used for nuclear fuel management during the transition process of the second-loaded module reactor, thereby reducing the use of low-enrichment fuel elements in the unit, increasing its average unloading burnup, shortening the overall transition process time, and reducing the amount of spent fuel, thereby lowering the operating costs of the nuclear power plant.

[0066] In step S24, during the execution of the fuel management information set, the fuel management information set is evaluated using a security evaluation method, wherein the fuel management information set includes the first fuel management information, the second fuel management information, and the third fuel management information; The relevant description may be as described above, and will not be repeated here.

[0067] In step S25, if the evaluation result indicates that the operating parameters of the multi-module pebble bed high temperature gas-cooled reactor during initial installation and transition meet the parameter requirements, the fuel management information collection is continued; The relevant description may be as described above, and will not be repeated here.

[0068] According to some embodiments, the operating parameter includes at least one of a maximum operating temperature, a maximum accident temperature, and a single-ball power.

[0069] According to some embodiments, the parameter requirement may be, for example, a requirement for determining whether to continue executing the fuel management information set. The parameter requirement is not a specific fixed requirement. For example, when the parameter threshold corresponding to the parameter requirement changes, the parameter requirement may also change accordingly.

[0070] According to some embodiments, when the evaluation result indicates that the operating parameters of the multi-module pebble bed high temperature gas-cooled reactor during initial installation and transition meet parameter requirements, the fuel management information collection is continued.

[0071] In step S26, when the evaluation result indicates that the operating parameters during the initial installation and transition of the multi-module pebble bed high temperature gas-cooled reactor do not meet the parameter requirements, the fuel management information set is adjusted, and a second adjusted fuel management information set is obtained and executed.

[0072] The relevant description may be as described above, and will not be repeated here.

[0073] For example, collected key parameters can be compared with preset parameter thresholds for the reactor. If the parameters do not exceed the preset thresholds, the fuel management information set can be continued. If they do, the fuel management information set cannot be continued and needs to be readjusted and evaluated. Key parameters include, but are not limited to, backup reactivity, shutdown margin, maximum fuel element operating temperature, maximum fuel element accident temperature, maximum fuel element burnup, reactivity control system value, single-sphere power, power density, and primary coolant inlet and outlet temperatures.

[0074] According to some embodiments, when the evaluation results indicate that the operating parameters of the multi-module pebble bed type high temperature gas-cooled reactor during the initial installation and transition process meet the parameter requirements, the fuel management information set continues to be executed; when the evaluation results indicate that the operating parameters of the multi-module pebble bed type high temperature gas-cooled reactor during the initial installation and transition process do not meet the parameter requirements, the fuel management information set is adjusted, and the second adjusted fuel management information set is obtained and executed. Therefore, it can be determined through the evaluation information whether to adjust the fuel management information set, which can improve the applicability and flexibility of nuclear fuel management and improve the matching of the fuel management information set with the multi-module pebble bed type high temperature gas-cooled reactor.

[0075] A block diagram of a nuclear fuel management device for a multi-module pebble bed high temperature gas-cooled reactor is shown according to an exemplary embodiment. Figure 5 , the apparatus 500 comprises: An information acquisition unit 501 is configured to acquire first fuel management information of a first module during initial installation and transition of a multi-module pebble bed high temperature gas-cooled reactor based on first input information corresponding to the first module, wherein the first module is the first module in the multi-module; The information acquisition unit 501 is further configured to acquire second fuel management information during the initial stacking and transition process of the second module based on the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module, wherein the second module is the next module adjacent to the first module in the multiple modules; The information acquisition unit 501 is further configured to acquire third fuel management information during the initial stack installation and transition of the fourth module based on low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to the fourth module, wherein the third module is a module preceding the fourth module in the multiple modules, and the fourth module is any module in the multiple modules except the first module and the second module. The information execution unit 502 is used to evaluate the fuel management information set using a security evaluation method during the execution of the fuel management information set, and execute the fuel management information set according to the evaluation result, wherein the fuel management information set includes the first fuel management information, the second fuel management information and the third fuel management information.

[0076] According to some embodiments, the information acquisition unit 501 is further configured to: In a case where a plurality of fuel management information sets corresponding to the plurality of modules are determined, obtaining evaluation information corresponding to each fuel management information set in the plurality of fuel management information sets; A target fuel management information set is obtained according to the evaluation information corresponding to each fuel management information set.

[0077] According to some embodiments, the information acquisition unit 501 is configured to acquire first fuel management information during initial installation and transition of a first module based on first input information corresponding to a multi-module pebble bed high temperature gas-cooled reactor, specifically for: Obtain structural design information of the multi-module pebble bed high-temperature gas-cooled reactor, power information of the multi-module pebble bed high-temperature gas-cooled reactor, and design information of the multi-module pebble bed high-temperature gas-cooled reactor; obtain first fuel management information during the initial installation and transition process of the first module, the first fuel management information including at least one of core loading information, fuel element enrichment information, fuel element and graphite ball ratio information, initial core establishment process information, transition process information, spent fuel sorting limit information, loading and replacement method information, and reactivity control information.

[0078] According to some embodiments, the information acquisition unit 501 is configured to acquire the second fuel management information of the second module during initial stacking and transition based on the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module, specifically for: Obtaining low-enrichment shallow burnup spent fuel element information corresponding to the first module, wherein the low-enrichment shallow burnup spent fuel element information corresponding to the first module includes quantity information and unloading burnup information of the low-enrichment shallow burnup spent fuel elements corresponding to the first module; Second fuel management information of the second module during the initial loading and transition process is obtained based on the quantity information of low-enrichment and shallow-burnup spent fuel elements corresponding to the first module, the unloading burnup information, the fuel element information corresponding to the second module, and the graphite ball information corresponding to the second module. The second fuel management information includes at least one of core loading capacity information, fuel element enrichment information, mixed fuel element and graphite ball ratio information, initial core establishment process information, transition process information, spent fuel sorting limit information, loading and replacement method information, and reactivity control information. The mixed fuel elements include the low-enrichment and shallow-burnup spent fuel elements corresponding to the first module and the fuel elements corresponding to the second module.

[0079] According to some embodiments, the information acquisition unit 501 is further configured to: When there are multiple units corresponding to the multi-module pebble bed high temperature gas-cooled reactor, the fuel management information set is adjusted according to the demand information of the multi-module pebble bed high temperature gas-cooled reactor of each unit in the multiple units to obtain a first adjusted fuel management information set.

[0080] According to some embodiments, the information execution unit 502 is configured to execute the fuel management information set according to the evaluation result, specifically to: If the evaluation results indicate that the operating parameters of the multi-module pebble bed high temperature gas-cooled reactor during initial installation and transition meet the parameter requirements, continue to execute the fuel management information collection; or, When the evaluation result indicates that the operating parameters of the multi-module pebble bed high temperature gas-cooled reactor during initial installation and transition do not meet parameter requirements, the fuel management information set is adjusted, and a second adjusted fuel management information set is obtained and executed.

[0081] According to some embodiments, the operating parameter includes at least one of a maximum operating temperature, a maximum accident temperature, and a single-ball power.

[0082] Regarding the apparatus in the above embodiment, the specific manner in which each module performs operations has been described in detail in the embodiment of the method, and will not be elaborated here.

[0083] In some or related embodiments, an information acquisition unit is used to obtain first fuel management information of the first module during the initial installation and transition process based on first input information corresponding to the multi-module pebble bed high temperature gas-cooled reactor, wherein the first module is the first module among the multiple modules; the information acquisition unit is also used to obtain second fuel management information of the second module during the initial installation and transition process based on low-enrichment shallow burnup spent fuel element information corresponding to the first module and second input information corresponding to the second module, wherein the second module is the next module adjacent to the first module among the multiple modules; the information acquisition unit is also used to obtain third fuel management information of the fourth module during the initial installation and transition process based on low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to the fourth module, wherein the third module is the module before the fourth module in the multiple modules, and the fourth module is any module in the multiple modules except the first and second modules; the information execution unit is used to evaluate the fuel management information set using a safety evaluation method during the execution of the fuel management information set, and execute the fuel management information set according to the evaluation result, wherein the fuel management information set includes the first fuel management information, the second fuel management information and the third fuel management information. Therefore, the first module can be determined based on the input information, and the modules after the first module can use the low-enrichment and shallow burnup fuel elements of the previous module in the transition process of the subsequent module stack, which can improve the accuracy of the fuel management information determination, shorten the transition process time, reduce the time to reach a balanced core, and reduce the cost of the power plant. The low-enrichment and shallow burnup fuel elements can be returned to the stack for utilization, which can improve the utilization efficiency of the low-enrichment and shallow burnup fuel elements, reduce the demand for new low-enrichment fuel elements, and reduce the nuclear fuel operating cost of the unit. It also reduces the number of low-enrichment spent fuel elements accordingly, reduces the storage and post-processing costs of the spent fuel elements, and thus improves the utilization rate of the low-enrichment fuel elements and reduces the cost of nuclear fuel.

[0084] Figure 6 A schematic block diagram of an example electronic device 600 that can be used to implement embodiments of the present disclosure is shown. The electronic device 600 is intended to represent various forms of digital computers, such as laptop computers, desktop computers, workstations, personal digital assistants, servers, blade servers, mainframe computers, and other suitable computers. The electronic device can also represent various forms of mobile devices, such as personal digital assistants, cellular phones, smartphones, wearable devices, and other similar computing devices. The components shown herein, their connections and relationships, and their functions are provided as examples only and are not intended to limit the implementation of the present disclosure described and / or claimed herein.

[0085] like Figure 6As shown, electronic device 600 includes a computing unit 601, which can perform various appropriate actions and processes according to a computer program stored in a read-only memory (ROM) 602 or a computer program loaded from a storage unit 608 into a random access memory (RAM) 603. Various programs and data required for the operation of electronic device 600 may also be stored in RAM 603. Computing unit 601, ROM 602, and RAM 603 are interconnected via a bus 604. An input / output (I / O) interface 605 is also connected to bus 604.

[0086] Multiple components in the electronic device 600 are connected to the I / O interface 605, including an input unit 606, such as a keyboard, a mouse, etc.; an output unit 607, such as various types of displays, speakers, etc.; a storage unit 608, such as a magnetic disk, an optical disk, etc.; and a communication unit 609, such as a network card, a modem, a wireless communication transceiver, etc. The communication unit 609 allows the electronic device 600 to exchange information / data with other devices via a computer network such as the Internet and / or various telecommunication networks.

[0087] The computing unit 601 can be any general-purpose and / or specialized processing component with processing and computing capabilities. Some examples of the computing unit 601 include, but are not limited to, a central processing unit (CPU), a graphics processing unit (GPU), various specialized artificial intelligence (AI) computing chips, various computing units running machine learning model algorithms, a digital signal processor (DSP), and any suitable processor, controller, microcontroller, etc. The computing unit 601 performs the various methods and processes described above. For example, in some embodiments, the above-described methods may be implemented as a computer software program tangibly embodied in a machine-readable medium, such as the storage unit 608. In some embodiments, part or all of the computer program may be loaded and / or installed onto the electronic device 600 via the ROM 602 and / or the communication unit 609. When the computer program is loaded into the RAM 603 and executed by the computing unit 601, one or more steps of the above-described methods may be performed. Alternatively, in other embodiments, the computing unit 601 may be configured to perform the above-described methods by any other suitable means (e.g., via firmware).

[0088] Various embodiments of the systems and techniques described above can be implemented in digital electronic circuit systems, integrated circuit systems, field programmable gate arrays (FPGAs), application specific integrated circuits (ASICs), application specific standard products (ASSPs), system-on-chip systems (SOCs), programmable logic devices (CPLDs), computer hardware, firmware, software, and / or combinations thereof. These various embodiments can include being implemented in one or more computer programs that are executable and / or interpreted on a programmable system that includes at least one programmable processor, which can be a special purpose or general purpose programmable processor that can receive data and instructions from a storage system, at least one input device, and at least one output device, and transmit data and instructions to the storage system, the at least one input device, and the at least one output device.

[0089] The program code for implementing the method of the present disclosure can be written in any combination of one or more programming languages. These program codes can be provided to a processor or controller of a general-purpose computer, a special-purpose computer, or other programmable data processing device so that when the program code is executed by the processor or controller, the functions / operations specified in the flow chart and / or block diagram are implemented. The program code can be executed entirely on the machine, partially on the machine, as a stand-alone software package, partially on the machine and partially on a remote machine, or entirely on a remote machine or server.

[0090] In the context of the present disclosure, a machine-readable medium may 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 may be a machine-readable signal medium or a machine-readable storage medium. A machine-readable medium may include, but is not limited to, an electronic, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any suitable combination of the foregoing. More specific examples of machine-readable storage media may include an electrical connection based on one or more wires, a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), optical fibers, a portable compact disk read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the foregoing.

[0091] To provide interaction with a user, the systems and techniques described herein can be implemented on a computer having: a display device (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor) for displaying information to the user; and a keyboard and pointing device (e.g., a mouse or trackball) through which the user can provide input to the computer. Other types of devices can also be used to provide interaction with the user; for example, the feedback provided to the user can be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user can be received in any form (including acoustic input, voice input, or tactile input).

[0092] The systems and techniques described herein can be implemented in a computing system that includes back-end components (e.g., as a data server), or a computing system that includes middleware components (e.g., an application server), or a computing system that includes front-end components (e.g., a user computer with a graphical user interface or web browser through which a user can interact with implementations of the systems and techniques described herein), or a computing system that includes any combination of such back-end components, middleware components, or front-end components. The components of the system can be interconnected by any form or medium of digital data communication (e.g., a communication network). Examples of communication networks include: a local area network (LAN), a wide area network (WAN), the Internet, and a blockchain network.

[0093] A computer system may include a client and a server. The client and server are typically remote from each other and typically interact via a communication network. This client-server relationship arises through computer programs running on the respective computers, establishing a client-server relationship. The server may be a cloud server, also known as a cloud computing server or cloud host. This server is a host product within the cloud computing service ecosystem that addresses the management difficulties and limited scalability of traditional physical servers and VPS services ("Virtual Private Servers" or "VPS"). The server may also be a server in a distributed system or a server integrated with blockchain.

[0094] It should be understood that the various forms of the processes shown above can be used to reorder, add, or delete steps. For example, the steps described in this disclosure can be performed in parallel, sequentially, or in a different order, as long as the desired results of the technical solutions disclosed in this disclosure can be achieved. This is not limited herein.

[0095] The above specific embodiments do not constitute a limitation on the scope of protection of this disclosure. Those skilled in the art will appreciate that various modifications, combinations, sub-combinations, and substitutions may be made based on design requirements and other factors. Any modifications, equivalent substitutions, and improvements made within the spirit and principles of this disclosure shall be included within the scope of protection of this disclosure.

Claims

1. A nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor, characterized in that: include: obtaining, according to first input information corresponding to a multi-module pebble bed high temperature gas-cooled reactor, first fuel management information during initial stacking and transition of a first module, wherein the first module is the first module of the multiple modules; acquiring, based on the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module, second fuel management information during the initial stacking and transition process of the second module, wherein the second module is the next module adjacent to the first module in the multiple modules; obtaining, based on low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to a fourth module, third fuel management information during initial stacking and transition of the fourth module, wherein the third module is a module preceding the fourth module in the multiple modules, and the fourth module is any module in the multiple modules other than the first module and the second module; During the execution of the fuel management information set, the fuel management information set is evaluated using a security evaluation method, and the fuel management information set is executed based on the evaluation result, wherein the fuel management information set includes the first fuel management information, the second fuel management information and the third fuel management information.

2. The method according to claim 1, characterized in that The method further comprises: When a plurality of fuel management information sets corresponding to the plurality of modules are determined, obtaining evaluation information corresponding to each fuel management information set in the plurality of fuel management information sets; A target fuel management information set is obtained according to the evaluation information corresponding to each fuel management information set.

3. The method according to claim 1, characterized in that The obtaining, according to first input information corresponding to the multi-module pebble bed high temperature gas-cooled reactor, first fuel management information during the initial installation and transition of the first module includes: Obtain structural design information of the multi-module pebble bed type high temperature gas-cooled reactor, power information of the multi-module pebble bed type high temperature gas-cooled reactor, and design information of the multi-module pebble bed type high temperature gas-cooled reactor; obtain first fuel management information during the initial installation and transition process of the first module, wherein the first fuel management information includes at least one of core loading information, fuel element enrichment information, fuel element and graphite ball ratio information, initial core establishment process information, transition process information, spent fuel sorting limit information, loading and replacement method information, and reactivity control information.

4. The method according to claim 3, characterized in that The step of obtaining the second fuel management information of the second module during the initial stacking and transition process according to the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module includes: Acquiring low-enrichment shallow burnup spent fuel element information corresponding to the first module, wherein the low-enrichment shallow burnup spent fuel element information corresponding to the first module includes quantity information and unloading burnup information of the low-enrichment shallow burnup spent fuel elements corresponding to the first module; Based on the quantity information of the low-enrichment and shallow-burnup spent fuel elements corresponding to the first module, the unloading burnup information, the fuel element information corresponding to the second module, and the graphite ball information corresponding to the second module, second fuel management information of the second module during the initial loading and transition process is obtained, wherein the second fuel management information includes at least one of core loading capacity information, fuel element enrichment information, mixed fuel element and graphite ball ratio information, initial core establishment process information, transition process information, spent fuel sorting limit information, loading and replacement method information, and reactivity control information, and the mixed fuel elements include the low-enrichment and shallow-burnup spent fuel elements corresponding to the first module and the fuel elements corresponding to the second module.

5. The method according to claim 1, wherein The method further comprises: When there are multiple units corresponding to the multi-module pebble bed high temperature gas-cooled reactor, the fuel management information set is adjusted according to the demand information of the multi-module pebble bed high temperature gas-cooled reactor of each unit in the multiple units to obtain a first adjusted fuel management information set.

6. The method according to claim 1, characterized in that The executing the fuel management information collection according to the evaluation result includes: If the evaluation result indicates that the operating parameters of the multi-module pebble bed high temperature gas-cooled reactor during initial installation and transition meet parameter requirements, continuing to execute the fuel management information set; or, When the evaluation result indicates that the operating parameters during the initial installation and transition of the multi-module pebble bed high temperature gas-cooled reactor do not meet the parameter requirements, the fuel management information set is adjusted, and a second adjusted fuel management information set is obtained and executed.

7. The method according to claim 6, characterized in that in, The operating parameters include at least one of a maximum operating temperature, a maximum accident temperature, and a single-ball power.

8. A nuclear fuel management device for a multi-module pebble bed high temperature gas-cooled reactor, characterized in that: include: an information acquisition unit, configured to acquire first fuel management information of a first module during initial installation and transition based on first input information corresponding to a multi-module pebble bed high temperature gas-cooled reactor, wherein the first module is the first module among the multiple modules; The information acquisition unit is further configured to acquire second fuel management information of the second module during initial stacking and transition based on the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module, wherein the second module is the next module adjacent to the first module in the multiple modules; The information acquisition unit is further configured to acquire third fuel management information of the fourth module during initial stacking and transition based on low-enrichment shallow burnup spent fuel element information corresponding to at least one third module and second input information corresponding to a fourth module, wherein the third module is a module preceding the fourth module in the multiple modules, and the fourth module is any module in the multiple modules other than the first module and the second module; An information execution unit is used to evaluate the fuel management information set using a security evaluation method during the execution of the fuel management information set, and execute the fuel management information set according to the evaluation result, wherein the fuel management information set includes the first fuel management information, the second fuel management information and the third fuel management information.

9. An electronic device, characterized in that: include: processor; a memory for storing instructions executable by the processor; The processor is configured to execute the instructions to implement the nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor according to any one of claims 1 to 7.

10. A storage medium storing instructions, characterized in that: When the instructions are executed on an electronic device, the electronic device is caused to execute the nuclear fuel management method for a multi-module pebble bed high temperature gas-cooled reactor according to any one of claims 1 to 7.

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