Method and device for nuclear fuel management of a multi-module pebble bed high temperature gas cooled reactor

Abstract

The present disclosure relates to the technical field of reactor fuel management, and particularly relates to a nuclear fuel management method of a multi-module pebble bed high temperature gas cooled reactor. The method comprises: obtaining first fuel management information in a first module initial loading and a transition process according to first input information corresponding to the multi-module pebble bed high temperature gas cooled reactor; obtaining second fuel management information in a second module initial loading and a transition process according to low enrichment shallow burnup spent fuel element information corresponding to the first module and second input information corresponding to the second module; obtaining third fuel management information in a fourth module initial loading and a transition process 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; and executing the fuel management information set according to an evaluation result of the fuel management information set in the process of executing the fuel management information set. The present disclosure can improve the accuracy of nuclear fuel management and improve the utilization rate of fuel elements.

Description

TECHNICAL FIELD

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

[0002] The pebble bed high temperature gas cooled reactor is a reactor that adopts spherical fuel elements, uses graphite as a moderator, and uses helium as a coolant. The pebble bed high temperature gas cooled reactor loads hundreds of thousands of spherical fuel elements into the reactor to reach a critical state that can be continuously and stably operated. During operation, the spherical fuel elements are continuously loaded into the core from the top of the reactor, and a corresponding number of fuel elements are continuously unloaded from the bottom of the core, so that the loading amount of the core remains unchanged. Therefore, how to manage the fuel elements during the initial loading of the reactor and the transition process becomes the focus. SUMMARY

[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 improve the utilization rate of fuel elements. The technical solution of the present disclosure is as follows:

[0004] According to a first aspect of the embodiment of the present disclosure, a nuclear fuel management method for a multi-module pebble bed high temperature gas cooled reactor is provided, comprising:

[0005] According to first input information corresponding to the multi-module pebble bed high temperature gas cooled reactor, first fuel management information in the initial loading of the reactor and the transition process of a first module is obtained, wherein the first module is the first module in the multi-module;

[0006] According to low-enrichment shallow burnup spent fuel element information corresponding to the first module and second input information corresponding to a second module, second fuel management information in the initial loading of the reactor and the transition process of the second module is obtained, wherein the second module is the next module adjacent to the first module in the multi-module;

[0007] 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, third fuel management information in the initial loading of the reactor and the transition process of the fourth module is obtained, wherein the third module is a module before the fourth module in the multi-module, and the fourth module is any module in the multi-module except the first module and the second module;

[0008] In the process of executing the fuel management information set, the fuel management information set is evaluated in a safety evaluation mode, 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.

[0009] According to some embodiments, the method further comprises:

[0010] In a case where a plurality of sets of fuel management information corresponding to the multi-module is determined, obtaining evaluation information corresponding to each set of fuel management information in the plurality of sets of fuel management information;

[0011] According to the evaluation information corresponding to each set of fuel management information, obtaining a target set of fuel management information.

[0012] According to some embodiments, the obtaining, according to the first input information corresponding to the multi-module pebble bed high temperature gas cooled reactor, of the first fuel management information in the initial loading and transition process of the first module comprises:

[0013] Obtaining structure 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, and obtaining the first fuel management information in the initial loading and transition process of the first module, the first fuel management information comprising at least one of core loading amount information, fuel element enrichment information, fuel element and graphite ball ratio information, initial core building process information, transition process information, spent fuel sorting limit value information, refueling mode information, and reactivity control information.

[0014] According to some embodiments, the obtaining, according to the low-enrichment low-burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module, of the second fuel management information in the initial loading and transition process of the second module comprises:

[0015] Obtaining the low-enrichment low-burnup spent fuel element information corresponding to the first module, wherein the low-enrichment low-burnup spent fuel element information corresponding to the first module comprises quantity information of the low-enrichment low-burnup spent fuel element corresponding to the first module and discharge burnup information;

[0016] According to the quantity information of the low-enrichment low-burnup spent fuel element corresponding to the first module, the discharge burnup information, fuel element information corresponding to the second module, and graphite ball information corresponding to the second module, obtaining the second fuel management information in the initial loading and transition process of the second module, wherein the second fuel management information comprises at least one of core loading amount information, fuel element enrichment information, mixed fuel element and graphite ball ratio information, initial core building process information, transition process information, spent fuel sorting limit value information, refueling mode information, and reactivity control information, the mixed fuel element comprising the low-enrichment low-burnup spent fuel element corresponding to the first module and the fuel element corresponding to the second module.

[0017] According to some embodiments, the method further comprises:

[0018] In a case where a plurality of units corresponding to the multi-module pebble bed high temperature gas cooled reactor are acquired, 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 plurality of units, to acquire a first adjusted fuel management information set.

[0019] According to some embodiments, the executing the fuel management information set according to the evaluation result comprises:

[0020] In a case where the evaluation result indicates that the operation parameters in the initial loading and the transition process of the multi-module pebble bed high temperature gas cooled reactor meet the parameter requirements, the fuel management information set is continuously executed;

[0021] Or,

[0022] In a case where the evaluation result indicates that the operation parameters in the initial loading and the transition process of the multi-module pebble bed high temperature gas cooled reactor do not meet the parameter requirements, the fuel management information set is adjusted to acquire and execute a second adjusted fuel management information set.

[0023] According to some embodiments, the operation parameters comprise at least one of an operation maximum temperature, an accident maximum temperature, and a single sphere power.

[0024] According to a second aspect of the embodiments of the present disclosure, a nuclear fuel management device of a multi-module pebble bed high temperature gas cooled reactor is provided, comprising:

[0025] An information acquisition unit is configured to acquire first fuel management information in an initial loading and a transition process of a first module according to first input information corresponding to the multi-module pebble bed high temperature gas cooled reactor, wherein the first module is a first module in the multi-module;

[0026] The information acquisition unit is further configured to acquire second fuel management information in an initial loading and a transition process of a second module 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 a next module adjacent to the first module in the multi-module;

[0027] The information acquisition unit is further configured to acquire third fuel management information in an initial loading and a transition process of a fourth module 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 a module before the fourth module in the multi-module, and the fourth module is any module in the multi-module except the first module and the second module;

[0028] The information execution unit is configured to evaluate the fuel management information set in a safety evaluation manner during execution of the fuel management information set, and execute the fuel management information set according to an 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 the embodiments of the present disclosure, an electronic device is provided, comprising:

[0029] a processor;

[0030] a memory for storing the processor-executable instructions;

[0031] The processor is configured to execute the instructions to implement the nuclear fuel management method of the multi-module pebble bed high temperature gas cooled reactor according to any one of the preceding aspects.

[0032] According to a fourth aspect of the embodiments of the present disclosure, a storage medium is provided, which, when instructions in the storage medium are executed by a processor of an electronic device, enables the electronic device to perform the nuclear fuel management method of the multi-module pebble bed high temperature gas cooled reactor according to any one of the preceding aspects.

[0033] According to a fifth aspect of the embodiments of the present disclosure, a computer program product is provided, comprising a computer program which, when executed by a processor, implements the method according to any one of the preceding aspects.

[0034] The technical solutions provided by the embodiments of the present disclosure at least bring the following beneficial effects:

[0035] In some or related embodiments, the first fuel management information in the initial loading and transition process of the first module is obtained according to the corresponding first input information of the multi-module pebble bed high temperature gas cooled reactor, wherein the first module is the first module in the multi-module; the second fuel management information in the initial loading and transition process of the second module is obtained according to the corresponding low enrichment and shallow burnup spent fuel element information of the first module and the corresponding second input information of the second module, wherein the second module is the next module adjacent to the first module in the multi-module; the third fuel management information in the initial loading and transition process of the fourth module is obtained according to the corresponding low enrichment and shallow burnup spent fuel element information of at least one third module and the corresponding second input information of the fourth module, wherein the third module is the module before the fourth module in the multi-module, and the fourth module is any module in the multi-module except the first module and the second module; in the process of executing the fuel management information set, the safety evaluation method is used to evaluate the fuel management information set, 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 according to the input information, the low enrichment and shallow burnup fuel elements of the previous module can be used in the transition process of the subsequent module, the accuracy of the fuel management information determination can be improved, the transition process time can be shortened, the time to reach the balanced core can be reduced, the cost of the power plant can be reduced, the low enrichment and shallow burnup fuel elements can be reused, the utilization efficiency of the low enrichment and shallow burnup fuel elements can be improved, the demand for low enrichment and new fuel elements can be reduced, the operation cost of the nuclear fuel of the unit can be reduced, and the number of low enrichment and spent fuel elements is correspondingly reduced, the storage and reprocessing cost of the spent fuel elements is reduced, thereby the utilization rate of the low enrichment and fuel elements can be improved, and the cost of the nuclear fuel is reduced.

[0036] It should be understood that the above general description and the following detailed description are only exemplary and explanatory, and cannot limit the present disclosure. BRIEF DESCRIPTION OF DRAWINGS

[0037] The accompanying drawings incorporated in the specification and forming a part of it, illustrate embodiments consistent with the present disclosure and, together with the description, serve to explain the principles of the disclosure without imposing undue limitation on the disclosure.

[0038] Figure 1 is a flow chart of a first nuclear fuel management method of a multi-module pebble bed high temperature gas cooled reactor provided by the embodiments of the present disclosure;

[0039] Figure 2is a flowchart of a second nuclear fuel management method of a multi-module pebble bed high temperature gas cooled reactor provided by an embodiment of the present disclosure.

[0040] Figure 3 is an example schematic diagram of a structure of a spherical fuel element provided by an embodiment of the present disclosure.

[0041] Figure 4 is an example schematic diagram of a change in discharge burnup of a low-enrichment fuel element of a pebble bed high temperature gas cooled reactor provided by an embodiment of the present disclosure.

[0042] Figure 5 is a block diagram of a nuclear fuel management device of a multi-module pebble bed high temperature gas cooled reactor according to an example embodiment.

[0043] Figure 6 is an example schematic diagram of an electronic device according to an example embodiment. DETAILED DESCRIPTION

[0044] In order for those skilled 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 described clearly and completely below with reference to the drawings.

[0045] The embodiments of the present disclosure provide a nuclear fuel management method, device, electronic equipment and storage medium of a multi-module pebble bed high temperature gas cooled reactor. In some embodiments, the nuclear fuel management method of the multi-module pebble bed high temperature gas cooled reactor and the information processing method, communication method and other terms can be replaced with each other, the nuclear fuel management device of the multi-module pebble bed high temperature gas cooled reactor and the information processing device, communication device and other terms can be replaced with each other, and the information processing system, communication system and other terms can be replaced with each other.

[0046] The embodiments of the present disclosure are not exhaustive, but are only schematic of some embodiments, and are not specific limitations on the protection scope of the present disclosure. In the case of no contradiction, each step in an embodiment can be implemented as an independent embodiment, and the steps can be combined arbitrarily, for example, the scheme after removing some steps in an embodiment can also be implemented as an independent embodiment, and the order of the steps in an embodiment can be exchanged arbitrarily, in addition, the optional implementation manners in an embodiment can be combined arbitrarily; in addition, the embodiments can be combined arbitrarily, for example, some or all steps of different embodiments can be combined arbitrarily, an embodiment can be combined with optional implementation manners of other embodiments.

[0047] In each embodiment of the present disclosure, the terms and / or descriptions between the embodiments are consistent if there is no special description and logical conflict, and can be referred to each other, and the technical features in different embodiments can be combined to form a new embodiment according to their inherent logical relationship.

[0048] The terms used in the embodiments of the present disclosure are merely used to describe specific embodiments, and are not used to limit the present disclosure.

[0049] In the embodiments of the present disclosure, unless otherwise specified, the elements represented by the singular form, such as “one”, “an”, “the”, “above”, “said”, “preceding”, “this”, etc., can represent “one and only one”, or “one or more”, “at least one”, etc. For example, in the case of using articles such as “a”, “an”, “the” in English in translation, the noun after the article can be understood as a singular expression, or as a plural expression.

[0050] In the embodiments of the present disclosure, “plurality” means two or more.

[0051] In some embodiments, the terms “at least one of”, “one or more of”, “a plurality of”, “multiple”, etc. can be replaced with each other.

[0052] The prefix words “first”, “second”, etc. in the embodiments of the present disclosure are merely used to distinguish different description objects, and do not constitute a limitation on the position, order, priority, quantity or content of the description objects. The description of the description objects is referred to the description in the claims or embodiments, and should not be considered as redundant limitation because of the use of the prefix words. For example, the description objects are “fields”, and the ordinal words before “fields” in “first field” and “second field” do not limit the position or order between “fields”, and “first” and “second” do not limit whether the “fields” modified thereby are in the same message or not, nor limit the order of “first field” and “second field”. For another example, the description objects are “levels”, and the ordinal words before “levels” in “first level” and “second level” do not limit the priority between “levels”. For another example, the quantity of the description objects is not limited by the ordinal words, and can be one or more. For example, “first device”, wherein the quantity of “devices” can be one or more. In addition, the objects modified by different prefix words can be the same or different, for example, the description objects are “devices”, and “first device” and “second device” can be the same device or different devices, and the types thereof can be the same or different. For another example, the description objects are “information”, and “first information” and “second information” can be the same information or different information, and the contents thereof can be the same or different.

[0053] In some embodiments, a "terminal" or "terminal device" can be referred to as a "user equipment" (UE), a "user terminal," a "mobile station" (MS), a "mobile terminal" (MT), a subscriber station, a mobile unit, a subscriber unit, a wireless unit, a remote unit, a mobile device, a wireless device, a wireless communication device, a remote device, a mobile subscriber station, an access terminal, a mobile terminal, a wireless terminal, a remote terminal, a handset, a user agent, a mobile client, a client, etc.

[0054] In some embodiments, data, information, etc. can be acquired after getting user consent.

[0055] It should be noted that the terms "first", "second", etc. in the specification and claims of the present disclosure and above-described figures are used to distinguish similar objects, and do not necessarily have to be used to describe a specific order or sequence. It should be understood that the data thus used can be interchanged under appropriate circumstances, so that the embodiments of the present disclosure described herein can be implemented in an order other than that illustrated or described herein. The implementation described in the following exemplary embodiments does not represent all the implementations consistent with the present disclosure. Rather, they are merely examples of devices and methods consistent with some aspects of the present disclosure as detailed in the appended claims.

[0056] Figure 1 is a flowchart of a first nuclear fuel management method of a multi-module pebble bed high temperature gas cooled reactor provided by an embodiment of the present disclosure, as shown in Figure 1 The nuclear fuel management method of the multi-module pebble bed high temperature gas cooled reactor can be used in the multi-module pebble bed high temperature gas cooled reactor initial loading and transition process nuclear fuel management scenarios, including the following steps:

[0057] In step S11, according to first input information corresponding to the multi-module pebble bed high-temperature gas-cooled reactor, first fuel management information in the first module initial loading reactor and in the transition process is obtained, wherein the first module is the first module in the multi-module.

[0058] In some embodiments, the execution subject of the embodiments of the present disclosure may, for example, be an electronic device. The electronic device is not particularly limited to a fixed electronic device. For example, the electronic device may also change accordingly when the device identity changes. For example, the electronic device may also change accordingly when the structure of the electronic device changes. Among them, the execution subject of the embodiments of the present disclosure may also be a server, which may be a single server, or a server cluster, and the embodiments of the present disclosure do not limit this.

[0059] According to some embodiments, the multi-module pebble bed high-temperature gas-cooled reactor may, for example, be a reactor that adopts spherical fuel elements, uses graphite as a moderator, and uses helium as a coolant. The most notable fuel management feature of this kind of reactor is that it can be refueled without stopping the reactor, that is, it can be refueled during operation. The multi-module pebble bed high-temperature gas-cooled reactor is not particularly limited to a fixed reactor. For example, the multi-module pebble bed high-temperature gas-cooled reactor may also change accordingly when the number of modules corresponding to the multi-module pebble bed high-temperature gas-cooled reactor changes. For example, the multi-module pebble bed high-temperature gas-cooled reactor may also change accordingly when the spherical fuel elements change.

[0060] Among them, “high temperature” in the high-temperature gas-cooled reactor (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, it may be higher than the temperature of a water-cooled reactor. The temperature of the high-temperature gas-cooled reactor can reach 700°C to 950°C, or greater than 950°C.

[0061] In some embodiments, the first input information may, for example, be input information corresponding to the first module. Different modules may correspond to different input information. The first input information may, for example, be input information corresponding to the first module, information input for the first module. The first input information is distinguished from the remaining input information, and is not particularly limited to a fixed information. For example, the first input information may also change accordingly when the number of information of the first input information changes. For example, the first input information may also change accordingly when the specific information of the first input information changes.

[0062] According to some embodiments, the first module may be the first module in the multi-module pebble bed high-temperature gas-cooled reactor, that is, the first module in the multi-module. The first module is not particularly limited to a fixed module. For example, the first module may also change accordingly when the module identity of the first module changes.

[0063] According to some embodiments, the initial loading refers to a state that the core active region is fully loaded by fuel elements and graphite spheres in a proportional and uniform manner, and the reactivity can reach a full power operation state. The transition process may, for example, refer to a process of transitioning from the initial loading state to an equilibrium state, and may, for example, involve analysis of criticality, power change, burnup change, and the like.

[0064] According to some embodiments, the first fuel management information may, for example, be used to refer to the management information of the first module for burning in the initial loading and the transition process. The burning management information does not refer to a fixed information. For example, when the first input information changes, the first burning management information may also change accordingly. Among them, the first in the first burning management information is used to distinguish from the rest of the burning management information. For example, when the number of information corresponding to the first burning management information changes, the first burning management information may also change accordingly.

[0065] In some embodiments, according to the first input information corresponding to the multi-module pebble bed type high temperature gas cooled reactor, the first fuel management information in the initial loading and the transition process of the first module is obtained, wherein the first module is the first module in the multi-module.

[0066] In step S12, 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, the second fuel management information in the initial loading and the transition process of the second module is obtained, wherein the second module is the next module adjacent to the first module in the multi-module;

[0067] According to some embodiments, the low enrichment shallow burnup spent fuel element information corresponding to the first module may, for example, be related information of the first module discharging low enrichment spent fuel elements. The low enrichment shallow burnup spent fuel element information corresponding to the first module may, for example, include the number and discharge burnup. The low enrichment shallow burnup spent fuel element information corresponding to the first module does not refer to a fixed information. For example, when 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.

[0068] In some embodiments, the second module may, for example, be the next module adjacent to the first module in the multi-module, that is, the second module in the multi-module. The second in the second module is used to distinguish from the rest of the modules. It does not refer to a fixed module.

[0069] According to some embodiments, the second input information may, for example, be the input information corresponding to the second module. Among them, different modules may, for example, correspond to different input information. The second fuel management information may, for example, be the fuel management information corresponding to the second module.

[0070] In some embodiments, the second fuel management information of the second module during the initial loading and the transition process is obtained according to the low-enrichment light-burnup spent fuel element information corresponding to the first module and the second input information corresponding to the second module.

[0071] In step S13, the third fuel management information of the fourth module during the initial loading and the transition process is obtained according to the low-enrichment light-burnup spent fuel element information corresponding to at least one third module and the second input information corresponding to the fourth module, wherein the third module is a module before the fourth module in the plurality of modules, and the fourth module is any module in the plurality of modules except the first module and the second module.

[0072] According to some embodiments, the third module is a plurality of modules before the fourth module in the plurality of modules or all the modules. The fourth module is any module in the plurality of modules except the first module and the second module. That is, the fuel management information of the third module and each module after the third module in the plurality of modules can be determined according to the input information of the module and the low-enrichment light-burnup spent fuel element information of all the modules before the module.

[0073] In some embodiments, the fuel management information of the third module and each module after the third module in the plurality of modules can be determined according to the input information of the module and the low-enrichment light-burnup spent fuel element information of at least one module before the module.

[0074] In some embodiments, the third fuel management information of the fourth module during the initial loading and the transition process is obtained according to the low-enrichment light-burnup spent fuel element information corresponding to at least one third module and the second input information corresponding to the fourth module, wherein the third module is a module before the fourth module in the plurality of modules, and the fourth module is any module in the plurality of modules except the first module and the second module.

[0075] In step S14, during the execution of the fuel management information set, the fuel management information set is evaluated by 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.

[0076] According to some embodiments, the safety evaluation method can be a method for determining whether each fuel management information in the fuel management information set is safe to execute. The safety evaluation method can correspond to the plurality of modules, for example, and can also correspond to each module. The safety evaluation method can include one or more of the maximum operating temperature, the maximum accident temperature, the single sphere power, etc.

[0077] In some embodiments, the set of fuel management information may, for example, include first fuel management information, second fuel management information, and third fuel management information, that is, each of the fuel management information needs to be evaluated.

[0078] According to some embodiments, in the process of executing the set of fuel management information, the set of fuel management information is evaluated in a safety evaluation manner, and the set of fuel management information is executed according to the evaluation result, wherein the set of fuel management information includes first fuel management information, second fuel management information, and third fuel management information.

[0079] In some or related embodiments, the first fuel management information in the initial loading and transition process of the first module is obtained according to the corresponding first input information of the multi-module pebble bed high temperature gas cooled reactor, wherein the first module is the first module in the multi-module; the second fuel management information in the initial loading and transition process of the second module is obtained according to the corresponding low-enrichment shallow burnup spent fuel element information of the first module and the corresponding second input information of the second module, wherein the second module is the next module adjacent to the first module in the multi-module; the third fuel management information in the initial loading and transition process of the fourth module is obtained according to the corresponding low-enrichment shallow burnup spent fuel element information of at least one third module and the corresponding second input information of the fourth module, wherein the third module is a module before the fourth module in the multi-module, and the fourth module is any module in the multi-module except the first module and the second module; in the process of executing the set of fuel management information, the set of fuel management information is evaluated in a safety evaluation manner, and the set of fuel management information is executed according to the evaluation result, wherein the set of fuel management information includes first fuel management information, second fuel management information, and third fuel management information. Therefore, the first module can be determined according to the input information, the low-enrichment shallow burnup spent fuel element of the module before the first module can be used in the transition process of the reactor of the subsequent module, that is, the low-enrichment shallow burnup spent fuel element discharged from the module that has been put into operation earlier can be used in the transition process of the reactor of the subsequent module by taking advantage of the difference in loading time of each module, the accuracy of the determination of the fuel management information can be improved, the length of the transition process can be shortened, the time to reach the balanced core can be reduced, the cost of the power plant can be reduced, the low-enrichment shallow burnup spent fuel element can be reused, the utilization efficiency of the low-enrichment shallow burnup spent fuel element can be improved, the demand for low-enrichment new fuel elements can be reduced, the operation cost of the nuclear fuel of the unit can be reduced, and the number of low-enrichment spent fuel elements is correspondingly reduced, the storage and reprocessing cost of the spent fuel elements is reduced, thereby the utilization rate of the low-enrichment fuel elements can be improved, and the cost of the nuclear fuel can be reduced.

[0080] Figure 2 is a flowchart of a second nuclear fuel management method of a multi-module pebble bed high temperature gas cooled reactor provided by the embodiments of the present disclosure, asFigure 2 As shown, the nuclear fuel management method of the multi-module pebble bed type high temperature gas cooled reactor can be used in the initial loading and transition process nuclear fuel management scenarios of the multi-module pebble bed type high temperature gas cooled reactor, including the following steps:

[0081] In step S21, according to the first input information corresponding to the multi-module pebble bed type high temperature gas cooled reactor, the first fuel management information in the initial loading and transition process of the first module is obtained, wherein the first module is the first module in the multi-module;

[0082] For example, the related description can be as described above, which will not be repeated here.

[0083] In some embodiments, the pebble bed type high temperature gas cooled reactor can load hundreds of thousands of spherical fuel elements into the reactor to reach a critical state that can be continuously and stably operated. During operation, the spherical fuel elements can be continuously loaded into the core from the top of the reactor, while a corresponding number of fuel elements are continuously unloaded from the bottom of the core, keeping the core load unchanged. The unloaded fuel elements are measured by the burnup measurement system, and if the predetermined burnup depth is not reached, they are sent back to the reactor for use; the fuel elements that reach the predetermined burnup are unloaded from the core as spent fuel and stored in the spent fuel tank. The structure of the spherical fuel elements can be as described above, for example. Figure 3 As shown, P y The C layer is a pyrolytic carbon layer. An example schematic diagram of the change in discharge burnup of the low enrichment fuel elements of the pebble bed type high temperature gas cooled reactor is as shown in Figure 4 As shown, most of the low enrichment fuel elements are not completely used up before being discharged from the core as spent fuel elements, which causes a great waste in economy. Therefore, recycling low enrichment fuel elements can reduce costs. Figure 4

[0084] According to some embodiments, in the early stage of the initial loading and transition process of the pebble bed type high temperature gas cooled reactor, the core fissile products are limited and there is basically no neutron poison, so the core can be critical with less fissile material than the equilibrium core. Therefore, the initial loading core of the pebble bed type high temperature gas cooled reactor can be composed of low enrichment fuel elements (compared to high enrichment fuel elements of the equilibrium core. For example, the high temperature gas cooled reactor core can be composed of high and low enrichment fuel elements and graphite balls, wherein the enrichment of the high and low enrichment fuel elements can be 8.5% and 4.2%, respectively), and the graphite balls can be pure graphite elements with the same size as the fuel elements and no uranium inside.

[0085] ​According to some embodiments, the pebble bed type high temperature gas cooled reactor adopts a certain proportion of mixed fuel composed of unused low enrichment fuel elements and graphite balls for initial core establishment, and after the initial core establishment is completed, a transition process is still needed to reach the equilibrium core, wherein the proportion of the unused low enrichment fuel elements and the graphite balls may be, for example, 7:8, and the embodiments of the present disclosure are not limited thereto. The above process may include:

[0086] (1) The reactor is operated at a certain power, and the graphite balls are unloaded in batches, while the same number of low enrichment fuel elements are loaded. This is manifested as the total loading amount of mixed fuel in the core is unchanged, the number of graphite balls gradually decreases, and the number of low enrichment fuel elements gradually increases, until the core is composed of low enrichment fuel elements. Subsequently, the core will start to discharge low enrichment spent fuel elements (with lower burnup level).

[0087] (2) The reactor continues to operate at a certain power, and during the operation, the low enrichment spent fuel elements are continuously discharged (the discharge burnup gradually increases), while the same amount of high enrichment fuel elements are loaded. This is manifested as the total loading amount of fuel elements in the core is unchanged, the number of low enrichment fuel elements gradually decreases, and the number of high enrichment fuel elements gradually increases, until the core is composed of high enrichment fuel elements, and the equilibrium core state is reached.

[0088] In some embodiments, for a multi-module pebble bed type high temperature gas cooled reactor, due to the sequential loading and commissioning of each module, the loading of the first module and the last module will be different in time, which may be, for example, half a year; if the same initial loading and transition process scheme is adopted, the time required for each module is the same, which may be, for example, about 3 years of full power operation, i.e. about 1100 effective full power days (EFPD). Therefore, the initial loading and transition process nuclear fuel management scheme of the unit can be developed, and the initial loading and transition process plan of each module can be developed as an input condition for the development of the nuclear fuel management scheme.

[0089] According to some embodiments, according to the first input information corresponding to the multi-module pebble bed type high temperature gas cooled reactor, the first fuel management information in the initial loading and transition process of the first module is obtained, including:

[0090] Obtaining 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, design information of the multi-module pebble bed high temperature gas cooled reactor, obtaining first fuel management information in the initial loading and transition process of the first module, the first fuel management information including at least one of in-core loading information, fuel element enrichment information, fuel element and graphite ball ratio information, initial core building process information, transition process information, spent fuel sorting limit value information, refueling mode information, and reactivity control information. Therefore, the fuel management information can be determined through the corresponding input information, the accuracy of the fuel management information determination can be improved, and the accuracy of the fuel management of the first module can be improved.

[0091] In some embodiments, the first module, i.e., the first module, cannot transition using low-enrichment shallow burnup spent fuel elements of other modules, so it is necessary to determine the fuel management information of the first module. The number and discharge burnup of the low-enrichment shallow burnup spent fuel elements discharged in the transition process of the first module will be used as the selection of the fuel management scheme of the initial loading and transition process of the subsequent module.

[0092] In step S22, the second fuel management information in the initial loading and transition process of the second module is obtained according to the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the corresponding second input information of the second module, wherein the second module is the next module adjacent to the first module in the multi-module;

[0093] Wherein, the relevant description may, for example, be as described above, and will not be repeated here.

[0094] According to some embodiments, the second fuel management information in the initial loading and transition process of the second module is obtained according to the low-enrichment shallow burnup spent fuel element information corresponding to the first module and the corresponding second input information of the second module, comprising:

[0095] 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 discharge burnup information of the low-enrichment shallow burnup spent fuel element corresponding to the first module;

[0096] According to the quantity information of the low-enrichment shallow burn-up spent fuel elements corresponding to the first module, the discharged burn-up information, the fuel element information corresponding to the second module, and the graphite sphere information corresponding to the second module, second fuel management information in the initial loading and transition process of the second module is obtained, wherein the second fuel management information includes at least one of the core loading amount information, the fuel element enrichment information, the mixed fuel element and graphite sphere ratio information, the initial loading core establishment process information, the transition process information, the spent fuel sorting limit value information, the refueling mode information, and the reactivity control information, and the mixed fuel element includes the low-enrichment shallow burn-up spent fuel elements corresponding to the first module and the fuel elements corresponding to the second module. Therefore, the second fuel management information can be determined by using the corresponding low-enrichment shallow burn-up spent fuel element information of the first module, the low-enrichment shallow burn-up fuel elements can be used in the transition process of the subsequent module, the transition process time can be shortened, the time to reach the balanced core can be reduced, and the cost of the power plant can be reduced.

[0097] In some embodiments, the second module, for example, the second module, can be transitioned according to unused fuel and spent fuel elements of the first module. The quantity and discharged burn-up of the spent fuel elements of the first module will be used as the selection of the nuclear fuel management scheme of the initial loading and transition process of the third and subsequent modules.

[0098] In step S23, according to the low-enrichment shallow burn-up spent fuel element information corresponding to at least one third module and the corresponding second input information of the fourth module, third fuel management information in the initial loading and transition process of the fourth module is obtained, wherein the third module is a module before the fourth module in the multi-module, and the fourth module is any module in the multi-module except the first module and the second module.

[0099] Wherein, the related description can be as described above, which will not be repeated here.

[0100] For example, the third module can be transitioned by using new fuel elements and spent fuel elements of the first module and the second module, and the selection of the nuclear fuel loading will be more. The quantity and discharged burn-up of the spent fuel elements discharged in the transition process of the third module will be used as the selection of the nuclear fuel management scheme of the initial loading and transition process of the fourth and subsequent modules. By analogy, the initial loading and transition process nuclear fuel management scheme of the nth module can be formulated in turn.

[0101] In some embodiments, there are many kinds of multi-module pebble bed high temperature gas cooled reactor initial loading and transition process nuclear fuel management schemes in theory, that is, a plurality of fuel management information sets can be corresponded, according to different operation requirements, application scenarios, and initial loading and transition process plans.

[0102] According to some embodiments, the method further includes:

[0103] In a case where a plurality of fuel management information sets corresponding to the multi-module is determined, evaluation information corresponding to each of the plurality of fuel management information sets is acquired;

[0104] According to the evaluation information corresponding to each of the plurality of fuel management information sets, a target fuel management information set is acquired. In a case where a plurality of fuel management information sets exists, the target fuel management information set can be determined according to the evaluation information, and the matching between the fuel management information set and the multi-module can be improved.

[0105] According to some embodiments, the plurality of fuel management information sets can be iterated, compared and analyzed comprehensively, and the target fuel management information set can be selected.

[0106] According to some embodiments, in a case where a plurality of units corresponding to the multi-module pebble bed high temperature gas cooled reactor exists, 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 plurality of units, and a first adjusted fuel management information set is acquired. Therefore, the spent fuel elements discharged from the first loading module reactor can be used for the nuclear fuel management of the transition process of the later loading module reactor, so as to reduce the amount of low enrichment fuel elements of the unit, improve the average discharge burnup, shorten the overall transition process time, and reduce the amount of spent fuel, thereby reducing the operation cost of the nuclear power plant.

[0107] In step S24, in the process of executing the fuel management information set, the fuel management information set is evaluated by using a safety evaluation method, wherein the fuel management information set includes first fuel management information, second fuel management information and third fuel management information;

[0108] For example, the related description can be as described above, which will not be repeated here.

[0109] In step S25, in a case where the evaluation result indicates that the operating parameters in the initial loading and transition process of the multi-module pebble bed high temperature gas cooled reactor meet the parameter requirements, the fuel management information set is continued to be executed;

[0110] For example, the related description can be as described above, which will not be repeated here.

[0111] According to some embodiments, the operating parameters include at least one of the operating maximum temperature, the accident maximum temperature and the single sphere power.

[0112] According to some embodiments, the parameter requirement can be a requirement for determining whether the fuel management information set can be continued to be executed, and the parameter requirement is not specific to a certain fixed requirement. For example, when the parameter threshold corresponding to the parameter requirement changes, the parameter requirement can also change accordingly.

[0113] According to some embodiments, in a case where the evaluation result indicates that the operation parameters in the initial loading and transition process of the multi-module pebble bed high temperature gas cooled reactor meet the parameter requirements, the fuel management information set is continued to be executed.

[0114] In step S26, in a case where the evaluation result indicates that the operation parameters in the initial loading and transition process 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.

[0115] For example, the relevant description can be as described above, which is not repeated here.

[0116] For example, the collected key parameters can be compared with the preset parameter threshold of the reactor. If each parameter does not exceed the preset parameter threshold, it is determined that the fuel management information set can be continued to be executed. If the preset parameter threshold is exceeded, the fuel management information set cannot be continued to be executed, and needs to be re-adjusted and evaluated. The key parameters include but are not limited to backup reactivity, shutdown margin, maximum operating temperature of fuel elements, maximum accident temperature of fuel elements, maximum burnup of fuel elements, reactivity control system value, single sphere power, power density, inlet and outlet temperature of primary coolant, etc.

[0117] According to some embodiments, in a case where the evaluation result indicates that the operation parameters in the initial loading and transition process of the multi-module pebble bed high temperature gas cooled reactor meet the parameter requirements, the fuel management information set is continued to be executed; in a case where the evaluation result indicates that the operation parameters in the initial loading and transition process 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. Therefore, it can be determined whether to adjust the fuel management information set through the evaluation information, which can improve the applicability and flexibility of nuclear fuel management and improve the matching of the fuel management information set and the multi-module pebble bed high temperature gas cooled reactor.

[0118] According to an exemplary embodiment, a block diagram of a nuclear fuel management device of a multi-module pebble bed high temperature gas cooled reactor is shown. Referring to Figure 5 The device 500 includes:

[0119] The information acquisition unit 501 is configured to acquire first fuel management information in the initial loading and transition process of a first module 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.

[0120] The information obtaining unit 501 is further configured to obtain second fuel management information of a second module in an initial loading and a transition process according to low-enrichment shallow-burn spent fuel element information corresponding to the first module and second input information corresponding to the second module, wherein the second module is a next module adjacent to the first module in the plurality of modules.

[0121] The information obtaining unit 501 is further configured to obtain third fuel management information of a fourth module in an initial loading and a transition process according to low-enrichment shallow-burn 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 plurality of modules, and the fourth module is any module in the plurality of modules except the first module and the second module.

[0122] The information executing unit 502 is configured to evaluate the set of fuel management information in a safe evaluation manner in a process of executing the set of fuel management information, and execute the set of fuel management information according to an evaluation result, wherein the set of fuel management information includes the first fuel management information, the second fuel management information, and the third fuel management information.

[0123] According to some embodiments, the information obtaining unit 501 is further configured to:

[0124] In a case where a plurality of sets of fuel management information corresponding to the plurality of modules is determined, the information obtaining unit 501 is further configured to obtain evaluation information corresponding to each set of fuel management information in the plurality of sets of fuel management information.

[0125] The information obtaining unit 501 is further configured to obtain a target set of fuel management information according to the evaluation information corresponding to each set of fuel management information.

[0126] According to some embodiments, the information obtaining unit 501 is configured to, when obtaining the first fuel management information of the first module in an initial loading and a transition process according to first input information corresponding to the plurality of module pebble bed high temperature gas cooled reactors, specifically configured to:

[0127] Obtain structure design information of the plurality of module pebble bed high temperature gas cooled reactors, power information of the plurality of module pebble bed high temperature gas cooled reactors, and design information of the plurality of module pebble bed high temperature gas cooled reactors, and obtain the first fuel management information of the first module in an initial loading and a transition process, wherein the first fuel management information includes at least one of core loading amount information, fuel element enrichment information, fuel element and graphite ball ratio information, initial core building process information, transition process information, spent fuel sorting limit value information, refueling mode information, and reactivity control information.

[0128] According to some embodiments, the information obtaining unit 501 is configured to, when obtaining the second fuel management information of the second module in an initial loading and a transition process according to low-enrichment shallow-burn spent fuel element information corresponding to the first module and second input information corresponding to the second module, specifically configured to:

[0129] 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 comprises quantity information of low-enrichment shallow-burnup spent fuel elements corresponding to the first module and discharge burnup information;

[0130] obtaining second fuel management information in the initial loading and transition process of the second module according to the quantity information of the low-enrichment shallow-burnup spent fuel elements corresponding to the first module, the discharge burnup information, the fuel element information corresponding to the second module and the graphite sphere information corresponding to the second module, wherein the second fuel management information comprises at least one of core loading information, fuel element enrichment information, mixed fuel element and graphite sphere ratio information, initial core establishment process information, transition process information, spent fuel sorting limit value information, refueling mode information and reactivity control information, and the mixed fuel element comprises the low-enrichment shallow-burnup spent fuel elements corresponding to the first module and the fuel elements corresponding to the second module.

[0131] According to some embodiments, the information obtaining unit 501 is further configured to:

[0132] In the case that the multiple-module pebble bed type high-temperature gas-cooled reactor corresponds to multiple units, adjusting the fuel management information set according to the demand information of the multiple-module pebble bed type high-temperature gas-cooled reactor in each unit of the multiple units to obtain a first adjusted fuel management information set.

[0133] According to some embodiments, the information executing unit 502 is configured to execute the fuel management information set according to the evaluation result, and specifically configured to:

[0134] In the case that the evaluation result indicates that the operating parameters in the initial loading and transition process of the multiple-module pebble bed type high-temperature gas-cooled reactor meet the parameter requirements, the fuel management information set is continuously executed;

[0135] or,

[0136] In the case that the evaluation result indicates that the operating parameters in the initial loading and transition process of the multiple-module pebble bed type high-temperature gas-cooled reactor do not meet the parameter requirements, the fuel management information set is adjusted to obtain and execute a second adjusted fuel management information set.

[0137] According to some embodiments, the operating parameters comprise at least one of the maximum operating temperature, the maximum accident temperature and the single sphere power.

[0138] As to the device in the above-mentioned embodiments, the specific manner in which each module performs the operation has been described in detail in the embodiments related to the method, and will not be described in detail here.

[0139] In some or related embodiments, the information obtaining unit is configured to obtain first fuel management information in the initial loading and transition process of the first module according to the 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 information obtaining unit is further configured to obtain second fuel management information in the initial loading and transition process of the second module according to the low enrichment and 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 multi-module; the information obtaining unit is further configured to obtain third fuel management information in the initial loading and transition process of the fourth module according to the low enrichment and shallow burnup spent fuel element information corresponding to at least one third module and the second input information corresponding to the fourth module, wherein the third module is a module before the fourth module in the multi-module, and the fourth module is any module in the multi-module except the first module and the second module; and the information executing unit is configured to evaluate the set of fuel management information in a safe evaluation manner during the execution of the set of fuel management information, and execute the set of fuel management information according to the evaluation result, wherein the set of fuel management information includes the first fuel management information, the second fuel management information and the third fuel management information. Therefore, the first module can be determined according to the input information, the low enrichment and shallow burnup spent fuel element of the module after the first module can be used in the transition process of the subsequent module, the accuracy of the determination of the fuel management information can be improved, the length of the transition process can be shortened, the time to reach the balanced core can be reduced, the cost of the power plant can be reduced, the low enrichment and shallow burnup spent fuel element can be reused, the utilization efficiency of the low enrichment and shallow burnup spent fuel element can be improved, the demand for low enrichment and new fuel elements can be reduced, the operation cost of the nuclear fuel of the unit can be reduced, the number of low enrichment and spent fuel elements is correspondingly reduced, the storage and reprocessing cost of the spent fuel element is reduced, the utilization rate of the low enrichment and fuel element is improved, and the cost of the nuclear fuel is reduced.

[0140] 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 laptops, desktops, tablets, personal digital assistants, servers, blade servers, mainframes, and other appropriate computers. The electronic device can also represent various forms of mobile devices such as personal digital assistants, cellular telephones, smartphones, wearable devices, and other similar computing devices. The components shown here, their connections and relationships, and their functions, are meant to be examples only, and are not intended to limit the implementations of the present disclosure described and / or claimed in this document.

[0141] As Figure 6As shown, the electronic device 600 includes a computing unit 601 that can perform various appropriate actions and processes in accordance with a computer program stored in a read-only memory (ROM) 602 or a computer program loaded from the storage unit 608 into a random access memory (RAM) 603. Various programs and data required for the operation of the electronic device 600 can also be stored in the RAM 603. The computing unit 601, the ROM 602, and the RAM 603 are connected to each other through a bus 604. An input / output (I / O) interface 605 is also connected to the bus 604.

[0142] A plurality of 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, and the like, an output unit 607 such as various types of displays, a speaker, and the like, a storage unit 608 such as a magnetic disk, an optical disk, and the like, and a communication unit 609 such as a network card, a modem, a wireless communication transceiver, and the like. The communication unit 609 allows the electronic device 600 to exchange information / data with other devices through a computer network such as the Internet and / or various telecommunication networks.

[0143] The computing unit 601 can be various general and / or special purpose processing components having 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 special-purpose artificial intelligence (AI) computing chips, various computing units running machine learning model algorithms, a digital signal processor (DSP), and any appropriate processor, controller, microcontroller, and the like. The computing unit 601 performs the various methods and processes described above. For example, in some embodiments, the above-described methods can be implemented as a computer software program that is tangibly embodied in a machine-readable medium, such as the storage unit 608. In some embodiments, part or all of the computer program can 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 can be performed. Alternatively, in other embodiments, the computing unit 601 can be configured to perform the above-described methods by any other appropriate means, such as by means of firmware.

[0144] The various embodiments of the systems and techniques described above can be implemented in digital electronic circuitry, integrated circuitry, a field programmable gate array (FPGA), an application specific integrated circuit (ASIC), a system on a chip (SOC), a load programmable logic device (CPLD), computer hardware, firmware, software, and / or combinations thereof. These various embodiments can include implementation in one or more computer programs that are executable and / or interpretable on a programmable system including at least one programmable processor, which can be special or general purpose, coupled to receive data and instructions from, and to transmit data and instructions to, a storage system, at least one input device, and at least one output device.

[0145] Program code for carrying out methods of the present disclosure can be written in any combination of one or more programming languages. The program code can be provided to a processor or controller of a general purpose computer, special purpose computer, or other programmable data processing apparatus to produce a machine, such that the program code, when executed by the processor or controller, produces the functions / operations specified in the flowcharts and / or the block diagrams. The program code can be executed entirely on a machine, partially on a machine, partially on a machine as a stand-alone software package, or entirely on a remote machine or server.

[0146] In the context of the present disclosure, a machine-readable medium can be a tangible medium that contains or stores a program for use by or in connection with an instruction execution system, apparatus, or device. The machine-readable medium can be a machine-readable signal medium or a machine-readable storage medium. A machine-readable medium can 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 the machine-readable storage medium will include one or more lines of electrical conductors, portable computer disks, hard disks, random access memory (RAM), read-only memory (ROM), erasable programmable read-only memory (EPROM or Flash memory), optical fibers, portable compact disc read-only memories (CD-ROMs), optical storage devices, magnetic storage devices, or any suitable combination of the foregoing.

[0147] To provide for interaction with a user, the systems and techniques described here 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 a pointing device (e.g., a mouse or a trackball) by which the user can provide input to the computer. Other kinds of devices can be used to provide for interaction with a user as well; for example, 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, speech, or tactile input.

[0148] The systems and techniques described here can be implemented in a computing system that includes a back end component (e.g., as a data server), or that includes a middleware component (e.g., an application server), or that includes a front end component (e.g., a user computer having a graphical user interface or a Web browser through which a user can interact with an implementation of the systems and techniques described here), or any combination of such back end, middleware, 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.

[0149] The computer system can include clients and servers. A client and server are generally remote from each other and typically interact through a communication network. The relationship of client and server arises by virtue of computer programs running on the respective computers and having a client-server relationship to each other. A server can be a cloud server, also known as a cloud computing server or cloud host, which is a host product in the cloud computing service system, to solve the defects of large management difficulty and weak business scalability in traditional physical host and VPS service ("Virtual Private Server", or simply "VPS"). The server can also be a server of a distributed system, or a server combined with a blockchain.

[0150] It should be understood that various forms of flow shown above can be used with reordering, adding or deleting steps. For example, the steps recited in the present disclosure can be performed in parallel, in series, or in different orders, as long as the desired results of the technical solutions disclosed in the present disclosure can be achieved, which are not limited herein.

[0151] The above detailed description does not limit the scope of the disclosure. Various modifications, combinations, sub-combinations and alternatives can be made to the detailed description. Any modification, equivalent replacement and improvement etc. made within the spirit and principle of the disclosure shall be included in the scope of the disclosure.

Claims

1. A method of nuclear fuel management for a multi-module pebble bed high temperature gas cooled reactor, characterized in that, The method comprises the following steps: obtaining first fuel management information in the initial loading and transition process of a first module of a multi-module pebble bed high-temperature gas-cooled reactor according to corresponding first input information of the multi-module pebble bed high-temperature gas-cooled reactor, wherein the first module is the first module in the multi-module; obtaining second fuel management information in the initial loading and transition process of a second module according to low-enrichment shallow-burn spent fuel element information corresponding to the first module and corresponding second input information of the second module, wherein the second module is the next module adjacent to the first module in the multi-module; obtaining third fuel management information in the initial loading and transition process of a fourth module according to low-enrichment shallow-burn spent fuel element information corresponding to at least one third module and corresponding second input information of the fourth module, wherein the third module is a module before the fourth module in the multi-module, and the fourth module is any module except the first module and the second module in the multi-module; in the process of executing the fuel management information set, evaluating the fuel management information set in a safety evaluation mode, and executing the fuel management information set according to the evaluation result, wherein the fuel management information set comprises the first fuel management information, the second fuel management information and the third fuel management information; wherein the obtaining of the first fuel management information in the initial loading and transition process of the first module according to the corresponding first input information of the multi-module pebble bed high-temperature gas-cooled reactor comprises: obtaining the structure design information of the multi-module pebble bed high-temperature gas-cooled reactor, the power information of the multi-module pebble bed high-temperature gas-cooled reactor, and the design information of the multi-module pebble bed high-temperature gas-cooled reactor, and obtaining the first fuel management information in the initial loading and transition process of the first module, wherein the first fuel management information comprises 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 value information, refueling mode information, and reactivity control information; wherein the obtaining of the second fuel management information in the initial loading and transition process of the second module according to the low-enrichment shallow-burn spent fuel element information corresponding to the first module and the corresponding second input information of the second module comprises: obtaining the low-enrichment shallow-burn spent fuel element information corresponding to the first module, wherein the low-enrichment shallow-burn spent fuel element information corresponding to the first module comprises quantity information and discharge burnup information of the low-enrichment shallow-burn spent fuel element corresponding to the first module; According to the quantity information of the low-enrichment shallow burn-up spent fuel elements corresponding to the first module, the discharge burn-up information, the fuel element information corresponding to the second module, and the graphite sphere information corresponding to the second module, second fuel management information in the initial loading and transition process of the second module is obtained, wherein 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 loading core establishment process information, transition process information, spent fuel sorting limit value information, refueling mode information, and reactivity control information, and the mixed fuel element includes the low-enrichment shallow burn-up spent fuel elements corresponding to the first module and the fuel elements corresponding to the second module.

2. The method of claim 1, wherein, The method further includes: In a case where a plurality of fuel management information sets corresponding to the multi-module are determined, evaluation information corresponding to each fuel management information set in the plurality of fuel management information sets is obtained; According to the evaluation information corresponding to each fuel management information set, a target fuel management information set is obtained.

3. The method of claim 1, wherein, The method further includes: In a case where a plurality of units corresponding to the multi-module pebble bed high-temperature gas-cooled reactor are obtained, the fuel management information set is adjusted according to the demand information of the multi-module pebble bed high-temperature gas-cooled reactor in each unit in the plurality of units, and a first adjusted fuel management information set is obtained.

4. The method of claim 1, wherein, The execution of the fuel management information set according to the evaluation result includes: In a case where the evaluation result indicates that the operating parameters in the initial loading and transition process of the multi-module pebble bed high-temperature gas-cooled reactor meet the parameter requirements, the fuel management information set is continuously executed; Or, In a case where the evaluation result indicates that the operating parameters in the initial loading and transition process of the multi-module pebble bed high-temperature gas-cooled reactor do not meet the parameter requirements, the fuel management information set is adjusted, a second adjusted fuel management information set is obtained, and the second adjusted fuel management information set is executed.

5. The method of claim 4, wherein, In which, The operating parameters include at least one of the highest operating temperature, the highest accident temperature, and the single sphere power.

6. A nuclear fuel management apparatus of a multi-module pebble bed high temperature gas-cooled reactor that implements the method of nuclear fuel management of any one of claims 1 to 5, characterized by, It includes: An information acquisition unit is configured to obtain first fuel management information in the initial loading and transition process of a first module according to first input information corresponding to a multi-module pebble bed high-temperature gas-cooled reactor, wherein the first module is a first module in the multi-module. The information acquisition unit is further configured to obtain second fuel management information in the initial loading and transition process of a second module according to low-enrichment shallow burn-up spent fuel element information corresponding to the first module and second input information corresponding to the second module, wherein the second module is a next module adjacent to the first module in the multi-module. The information acquisition unit is further configured to obtain third fuel management information in the initial loading and transition process of a fourth module according to low-enrichment shallow burn-up 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 multi-module, and the fourth module is any module in the multi-module except the first module and the second module. An information execution unit is configured to evaluate the fuel management information set in a safety evaluation manner 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 comprises the first fuel management information, the second fuel management information and the third fuel management information.

7. An electronic device, comprising: Comprise: a processor; a memory for storing instructions executable by the processor; wherein the processor is configured to execute the instructions to implement the method of nuclear fuel management of a multi-module pebble bed high temperature gas cooled reactor of any one of claims 1 to 5.

8. A storage medium, the storage medium storing instructions, wherein, When the instructions run on an electronic device, the electronic device is caused to perform the method of nuclear fuel management of a multi-module pebble bed high temperature gas cooled reactor of any one of claims 1 to 5.

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